JPH04290994A - Reactor container vessel - Google Patents
Reactor container vesselInfo
- Publication number
- JPH04290994A JPH04290994A JP3056300A JP5630091A JPH04290994A JP H04290994 A JPH04290994 A JP H04290994A JP 3056300 A JP3056300 A JP 3056300A JP 5630091 A JP5630091 A JP 5630091A JP H04290994 A JPH04290994 A JP H04290994A
- Authority
- JP
- Japan
- Prior art keywords
- pool
- containment vessel
- pressure
- pool water
- pressure suppression
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 409
- 230000001629 suppression Effects 0.000 claims abstract description 369
- 230000002093 peripheral effect Effects 0.000 claims description 68
- 230000001737 promoting effect Effects 0.000 claims description 68
- 238000001816 cooling Methods 0.000 claims description 51
- 239000000498 cooling water Substances 0.000 claims description 39
- 229910000831 Steel Inorganic materials 0.000 claims description 37
- 239000010959 steel Substances 0.000 claims description 37
- 238000012546 transfer Methods 0.000 claims description 37
- 238000001704 evaporation Methods 0.000 claims description 28
- 230000008020 evaporation Effects 0.000 claims description 28
- 238000000034 method Methods 0.000 claims description 25
- 239000012530 fluid Substances 0.000 claims description 21
- 229920006395 saturated elastomer Polymers 0.000 claims description 19
- 238000009833 condensation Methods 0.000 claims description 17
- 230000005494 condensation Effects 0.000 claims description 17
- 230000002209 hydrophobic effect Effects 0.000 claims description 16
- 239000002826 coolant Substances 0.000 claims description 13
- 239000000126 substance Substances 0.000 claims description 13
- 238000005192 partition Methods 0.000 claims description 8
- 238000007599 discharging Methods 0.000 claims description 7
- 238000009835 boiling Methods 0.000 claims description 4
- 230000001419 dependent effect Effects 0.000 claims description 2
- 238000000926 separation method Methods 0.000 claims description 2
- 230000001965 increasing effect Effects 0.000 abstract description 81
- 239000007789 gas Substances 0.000 abstract description 79
- 230000009471 action Effects 0.000 abstract description 36
- 230000005855 radiation Effects 0.000 abstract description 22
- 239000007792 gaseous phase Substances 0.000 abstract 1
- 230000000694 effects Effects 0.000 description 70
- 230000017525 heat dissipation Effects 0.000 description 67
- 241000196324 Embryophyta Species 0.000 description 18
- 230000007423 decrease Effects 0.000 description 9
- 238000010586 diagram Methods 0.000 description 6
- 230000006872 improvement Effects 0.000 description 6
- 238000002955 isolation Methods 0.000 description 6
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 4
- 238000009825 accumulation Methods 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 4
- 239000007788 liquid Substances 0.000 description 4
- 230000005484 gravity Effects 0.000 description 3
- 238000005338 heat storage Methods 0.000 description 3
- 238000012423 maintenance Methods 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 241001365789 Oenanthe crocata Species 0.000 description 2
- 230000008901 benefit Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 2
- 230000003247 decreasing effect Effects 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 229910052757 nitrogen Inorganic materials 0.000 description 2
- 229920002545 silicone oil Polymers 0.000 description 2
- 238000013517 stratification Methods 0.000 description 2
- 238000009423 ventilation Methods 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000008602 contraction Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000004044 response Effects 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【０００１】0001
【産業上の利用分野】本発明は原子炉格納容器内の事故
時の圧力上昇を抑制する技術に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a technique for suppressing a pressure rise in a nuclear reactor containment vessel during an accident.
【０００２】0002
【従来の技術】原子炉格納容器は、特開昭６３−７５５
９４ 号公報に開示されているように、炉心を内蔵した
原子炉圧力容器が配備される空間であるドライウエルと
圧力抑制室とを包含している。その圧力抑制室はプール
水を内蔵し、そのプール水領域である圧力抑制プールと
その上方の空間であるウエットウエルとから成り、ドラ
イウエルがベント管によりプール水中に連通されている
。この圧力抑制室は外周囲が外周プールに囲われている
。[Prior art] Nuclear reactor containment vessel is
As disclosed in the No. 94 publication, it includes a dry well and a pressure suppression chamber, which are spaces in which a reactor pressure vessel containing a reactor core is placed. The pressure suppression chamber contains pool water and consists of a pressure suppression pool, which is the pool water area, and a wet well, which is a space above the pressure suppression pool, and the dry well is communicated with the pool water by a vent pipe. This pressure suppression chamber is surrounded by a peripheral pool.
【０００３】この様な原子炉格納容器において、炉心で
加熱されて高温高圧蒸気と成った原子炉圧力容器内の冷
却材は原子炉圧力容器から原子炉格納容器外へ配管を通
して供給されるが、その配管の途中で破断が生じると、
高温高圧蒸気がドライウエル内に漏出（冷却材喪失の事
故）して充満し、ドライウエル内に充満されていた窒素
を同伴してベント管経由で圧力抑制プール水中に放出さ
れ、ここで蒸気は凝縮され、窒素は不凝縮性気体として
ウエットウエル内に蓄積される。この凝縮により圧力抑
制プール水の水温は高まり、外周プール水水温との間で
温度差を生じる。圧力抑制室と外周プールとの間の格納
容器壁は伝熱性のよい鋼製壁であるから、前述の温度差
を生じると、圧力抑制プール水が保有する熱は原子炉格
納容器の壁を通して外周プール水に移行する。この様に
、事故時に原子炉格納容器内の熱を他の動的機器を使用
せずに原子炉格納容器外に排出して原子炉格納容器内の
圧力を抑制し、もって原子炉格納容器の健全性を確実な
ものとする。In such a reactor containment vessel, the coolant inside the reactor pressure vessel, which is heated in the reactor core and turned into high-temperature, high-pressure steam, is supplied from the reactor pressure vessel to the outside of the reactor containment vessel through piping. If a break occurs in the middle of the pipe,
High-temperature, high-pressure steam leaks into the dry well (accident of loss of coolant) and is discharged into the pressure suppression pool water via the vent pipe, taking with it the nitrogen that had filled the dry well. Condensed, the nitrogen accumulates in the wet well as a non-condensable gas. This condensation increases the temperature of the pressure suppression pool water, creating a temperature difference between it and the outer pool water temperature. The containment vessel wall between the pressure suppression chamber and the outer peripheral pool is a steel wall with good heat conductivity, so when the above-mentioned temperature difference occurs, the heat held by the pressure suppression pool water passes through the reactor containment vessel wall and is transferred to the outer circumference. Transfer to pool water. In this way, in the event of an accident, the pressure inside the reactor containment vessel is suppressed by discharging the heat inside the reactor containment vessel to the outside of the reactor containment vessel without using other dynamic equipment, thereby reducing the pressure inside the reactor containment vessel. Ensure soundness.
【０００４】又、動的機器を用いないで自然に原子炉格
納容器からの放熱を促すものは、自然放熱型格納容器と
呼ばれ、動的機器を用いないので信頼性が良い。[0004] Also, a reactor containment vessel that naturally promotes heat radiation from the reactor containment vessel without using dynamic equipment is called a natural heat radiation type containment vessel, and is highly reliable because it does not use dynamic equipment.
【０００５】この様に、原子炉の安全設計で想定するこ
とになっている冷却材喪失の事故時に圧力抑制機能を有
する原子炉格納容器にあって、格納容器外周部に冷却水
プールを備えた自然放熱型格納容器は、圧力抑制室から
格納容器壁を介して外周プールへ熱を伝え格納容器を冷
却し、格納容器の圧力上昇を抑制する。この自然放熱型
格納容器を相対的に出力が大きいプラントに適用する場
合、事故時に炉心から格納容器内に放出される崩壊熱が
出力に比例して増大する結果、格納容器外への放熱量も
増大させる必要がある。[0005] In this way, the reactor containment vessel has a pressure suppression function in the event of a loss of coolant accident, which is assumed in the safety design of a nuclear reactor, and a cooling water pool is provided on the outer periphery of the containment vessel. A natural heat dissipation type containment vessel cools the containment vessel by transmitting heat from the pressure suppression chamber to the outer circumferential pool via the containment vessel wall, and suppresses pressure rise in the containment vessel. When this natural heat dissipation type containment vessel is applied to a plant with relatively large output, the decay heat released from the reactor into the containment vessel during an accident increases in proportion to the output, and as a result, the amount of heat released outside the containment vessel also increases. need to be increased.
【０００６】自然放熱型格納容器からの放熱量を増大す
る方法としては、圧力抑制室から外周プールへの伝熱面
積を増大させる方法がある。[0006] As a method for increasing the amount of heat dissipated from the natural heat dissipation type containment vessel, there is a method of increasing the heat transfer area from the pressure suppression chamber to the peripheral pool.
【０００７】原子炉格納容器壁を伝熱面として用いる場
合、格納容器径を大きくする方法と、ベント管水深を深
くして伝熱に有効な領域を高さ方向に拡げる方法によっ
て、伝熱面積を拡大することができる。しかし、原子炉
格納容器径の増大は格納容器の耐圧能力の低下をもたら
し、その耐圧能力の低下による圧力抑制室の許容温度の
低下を来たし、放熱特性の減少につながり好ましくない
。また、ベント管水深を深くすると、事故後初期に大量
の蒸気が急激に圧力抑制室に流入する際に圧力抑制プー
ル水の盛り上がりが大きくなるためプール水上方の空間
を高くしたり、圧力抑制室内の構造物の強度を増大する
する必要があり好ましくない。When using the reactor containment vessel wall as a heat transfer surface, the heat transfer area can be increased by increasing the containment vessel diameter and increasing the depth of the vent pipe to expand the area effective for heat transfer in the height direction. can be expanded. However, an increase in the diameter of the reactor containment vessel causes a decrease in the pressure withstanding capacity of the containment vessel, and the decrease in the pressure withstand capacity causes a decrease in the allowable temperature of the pressure suppression chamber, which is undesirable as it leads to a decrease in heat dissipation characteristics. In addition, if the vent pipe water depth is deepened, the pressure suppression pool water will rise larger when a large amount of steam suddenly flows into the pressure suppression chamber in the early stages after an accident. This is undesirable because it requires increasing the strength of the structure.
【０００８】格納容器径の拡大あるいはベント管水深を
深くすることなしに伝熱面積を拡大する従来技術として
、特開昭６４−９１０８９号公報及び特開平２−１８１
６９６号公報に記載のように、外周プール水を圧力抑制
室内部を通過する管により循環させ、格納容器壁を介し
ての自然放熱に加えて圧力抑制室内部を通過する管から
の放熱を利用した方法がある。[0008] As conventional techniques for expanding the heat transfer area without increasing the diameter of the containment vessel or increasing the water depth of the vent pipe, Japanese Patent Laid-Open Nos. 64-91089 and 2-181 disclose
As described in Publication No. 696, water from the outer pool is circulated through a pipe passing inside the pressure suppression chamber, and in addition to natural heat radiation through the walls of the containment vessel, heat radiation from the pipe passing inside the pressure suppression chamber is utilized. There is a method.
【０００９】他の従来技術として、日本原子力学会「１
９８９年秋の大会」で発表されたように、圧力抑制プー
ル内に対流促進板を設置し、圧力抑制プール下部領域に
おけるプール水の循環を促進させて、圧力抑制プール内
の温度成層化現象を緩和することにより、原子炉からの
熱を吸収するに有効な圧力抑制プール領域及び放熱のた
めの伝熱面積を上下に拡大する方法がある。[0009] As another conventional technology, the Atomic Energy Society of Japan ``1
As announced at the 1998 Autumn Conference, a convection promoting plate was installed inside the pressure suppression pool to promote the circulation of pool water in the lower area of the pressure suppression pool, thereby alleviating the temperature stratification phenomenon within the pressure suppression pool. By doing so, there is a method of vertically expanding the pressure suppression pool area effective for absorbing heat from the reactor and the heat transfer area for heat radiation.
【００１０】また、圧力抑制プールだけではなくウェッ
トウエルをも格納容器壁を利用して冷却する従来技術と
しては、特開平２−２２７６９９ 号に示されるように
、格納容器全体を流路で囲い、その流路に空気を流通さ
せて冷却する方法がある。[0010] Furthermore, as a conventional technique for cooling not only the pressure suppression pool but also the wet well using the wall of the containment vessel, as shown in Japanese Patent Application Laid-open No. 2-227699, the entire containment vessel is surrounded by a flow path. There is a method of cooling by circulating air through the flow path.
【００１１】[0011]
【発明が解決しようとする課題】上記の従来技術では、
圧力抑制プールからの放熱によって高温となった外周プ
ール水を循環させているため、ベント管出口より下側の
領域では、常に外周プール側の温度が先に高くなる。こ
のためその領域では外周プールから圧力抑制室に向かっ
て伝熱が起こり、ベント管出口より上方で外周プールへ
放熱した熱を下の領域で再び圧力抑制室に吸収する結果
となる。すなわち、ベント管出口より下側の領域での蓄
熱の増大は期待できるが、外周プールへの放熱面積的に
は増大ではなく減少の因子となる。また、この従来技術
では、伝熱管内の水の循環の継続性についても考慮され
ていない。水の循環は、伝熱管内と外周プール内の温度
の違いによる密度差に基づいている。伝熱管内と外周プ
ールの水は、圧力抑制室からの放熱により加熱され密度
が軽くなりプール上部に蓄積される。この蓄積は、伝熱
管と外周プールの両方で同様に起こるとともに、外周プ
ールが大気開放であることから最終的には両方の領域が
その飽和温度（１００℃）の水で満たされ、両領域に温
度差が確保できず水の循環が停止することになる。[Problem to be solved by the invention] In the above conventional technology,
Since the outer circumferential pool water, which has become hot due to heat radiation from the pressure suppression pool, is circulated, the temperature on the outer circumferential pool side always rises first in the region below the vent pipe outlet. Therefore, in that region, heat transfer occurs from the outer peripheral pool toward the pressure suppression chamber, resulting in the heat radiated to the outer peripheral pool above the vent pipe outlet being absorbed again into the pressure suppression chamber in the lower region. That is, although an increase in heat storage in the area below the vent pipe outlet can be expected, the area of heat radiation to the peripheral pool will be reduced rather than increased. Furthermore, this prior art does not take into consideration the continuity of water circulation within the heat exchanger tubes. Water circulation is based on the density difference due to the difference in temperature within the heat transfer tube and the outer pool. The water in the heat transfer tubes and the outer pool is heated by heat radiation from the pressure suppression chamber, becomes less dense, and accumulates in the upper part of the pool. This accumulation occurs in both the heat transfer tubes and the outer pool, and since the outer pool is open to the atmosphere, both areas will eventually be filled with water at its saturation temperature (100°C), and both areas will be Water circulation will stop because the temperature difference cannot be maintained.
【００１２】上記の原子力学会で発表された放熱量増大
に関する他の従来技術では、圧力抑制プール内に設置し
た対流促進板により圧力抑制プール内の水を循環させて
おり、上述の技術で考慮していなかった問題点を解消し
てベント管出口より下部の領域の活用および循環の継続
性を達成できるが、圧力抑制室と外周プール間の伝熱面
として原子炉格納容器壁のみを用いており、伝熱面積の
拡大が圧力抑制プールの高温領域の拡大量に制限される
ため、より一層の放熱量の拡大を望む場合に圧力抑制プ
ールの拡大を伴う。このことは原子炉格納容器の大型化
を伴う。[0012] In another conventional technology related to increasing the amount of heat dissipation announced at the above-mentioned Atomic Energy Society meeting, water in the pressure suppression pool is circulated by a convection promoting plate installed in the pressure suppression pool. However, it is possible to utilize the area below the vent pipe outlet and achieve continuity of circulation by solving the problems that previously existed, but only the reactor containment vessel wall is used as the heat transfer surface between the pressure suppression chamber and the peripheral pool. Since the expansion of the heat transfer area is limited to the amount of expansion of the high temperature region of the pressure suppression pool, when it is desired to further increase the amount of heat dissipation, the pressure suppression pool must be expanded. This entails increasing the size of the reactor containment vessel.
【００１３】上記の空気冷却を行う従来技術では、空気
流通による壁面での熱伝達率が、プール水中での対流熱
伝達率に比べて小さく、必要な放熱特性を達成するに大
きな伝熱面積を必要とするとともに、上述の圧力抑制プ
ールの許容温度を上昇させるという点についても考慮さ
れていない。[0013] In the above-mentioned conventional technology for air cooling, the heat transfer coefficient on the wall surface due to air circulation is smaller than the convective heat transfer coefficient in pool water, and a large heat transfer area is required to achieve the necessary heat dissipation characteristics. In addition, no consideration is given to increasing the permissible temperature of the pressure suppression pool as described above.
【００１４】これらの、従来技術による原子炉格納容器
の放熱特性を、より大出力な原子力プラントに適合すべ
く、より一層向上させるには、原子炉格納容器を大型化
して放熱面積を拡大することが考えられるが、原子炉格
納容器の大型化を伴う問題点がある。[0014] In order to further improve the heat dissipation characteristics of these conventional reactor containment vessels in order to make them suitable for higher output nuclear power plants, it is necessary to enlarge the reactor containment vessel and expand its heat dissipation area. is possible, but there are problems associated with increasing the size of the reactor containment vessel.
【００１５】したがって、本発明の目的は、大型化を伴
うことを極力抑制しつつも従来の原子炉格納容器の放熱
特性を向上させより大出力の原子力プラントに適用する
に好適な放熱手段を提供することににある。Therefore, an object of the present invention is to improve the heat dissipation characteristics of the conventional reactor containment vessel while suppressing the increase in size as much as possible, and to provide a heat dissipation means suitable for application to higher output nuclear power plants. There is something to do.
【００１６】[0016]
【課題を解決するための手段】第１手段は、炉心を内蔵
した原子炉圧力容器と、前記原子炉圧力容器が配備され
たドライウエルと、前記ドライウエルを収納した格納容
器と、プール水領域とドライウエル空間とから成る圧力
抑制室と、前記ドライウエルと前記プール水中とを連通
する流路とを備えた原子炉格納容器において、前記圧力
抑制室のウエットウエルに連通して他の室を備え、前記
他の室は原子炉の冷却材喪失事故時に前記プール水を包
含する室よりも低温の条件下と成る位置に配置されてい
ることを特徴とした原子炉格納容器である。[Means for Solving the Problems] A first means includes a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, and a pool water area. A reactor containment vessel comprising a pressure suppression chamber consisting of a dry well space and a flow path communicating the dry well and the pool water, the pressure suppression chamber communicating with the wet well of the pressure suppression chamber and connecting other chambers. The reactor containment vessel is characterized in that the other chamber is located at a position where the other chamber is under a lower temperature condition than the chamber containing the pool water in the event of a loss of coolant accident in the reactor.
【００１７】第２手段は、第１手段において、前記圧力
抑制室を前記プール水を包含する室と他の室とに分けて
、前記他の室は原子炉の冷却材喪失事故時に前記プール
水を包含する室よりも低温の条件下と成る位置に配置さ
れていることを特徴とした原子炉格納容器である。[0017] In the second means, in the first means, the pressure suppression chamber is divided into a chamber containing the pool water and another chamber, and the other chamber is configured to contain the pool water in the event of a reactor loss of coolant accident. A nuclear reactor containment vessel is characterized in that it is located at a location where the temperature is lower than that of the chamber containing the reactor containment vessel.
【００１８】第３手段は、第１又は２手段において、前
記格納容器は少なくとも圧力抑制室のプール水領域が前
記プール水と内面において接する鋼製の壁により構成さ
れ、前記鋼製の壁の外周面に接して外周プールを備えて
いることを特徴とした原子炉格納容器である。[0018] According to a third means, in the first or second means, the containment vessel is constituted by a steel wall in which at least the pool water area of the pressure suppression chamber is in contact with the pool water at the inner surface, and the outer periphery of the steel wall is This is a nuclear reactor containment vessel characterized by having an outer circumferential pool in contact with the surface.
【００１９】第４手段は、炉心を内蔵した原子炉圧力容
器と、前記原子炉圧力容器が配備されたドライウエルと
、前記ドライウエルを収納した格納容器と、プール水領
域とドライウエル空間とから成る圧力抑制室と、前記ド
ライウエルと前記プール水中とを連通する流路とを備え
た原子炉格納容器において、前記流路の前記プール水へ
の出口よりも高い位置に取水口が、同じく低い位置に排
水口が前記プール水中に開かれた循環流路を備え、前記
循環流路は少なくとも一部が前記格納容器の外側に通さ
れていることを特徴とした原子炉格納容器である。[0019] The fourth means includes a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel in which the dry well is housed, a pool water area, and a dry well space. In a reactor containment vessel comprising a pressure suppression chamber consisting of a pressure suppression chamber and a flow path communicating between the dry well and the pool water, a water intake is located at a higher position than the outlet of the flow path to the pool water, and a water intake is located at a position that is also lower than the outlet of the flow path to the pool water. The nuclear reactor containment vessel is characterized in that the reactor containment vessel is provided with a circulation flow path in which a drainage port is opened into the pool water, and at least a portion of the circulation flow path passes through the outside of the containment vessel.
【００２０】第５手段は、第４手段において、前記循環
流路の途中に冷却手段を備えたことを特徴とした原子炉
格納容器である。[0020] A fifth means is a reactor containment vessel according to the fourth means, characterized in that a cooling means is provided in the middle of the circulation flow path.
【００２１】第６手段は、炉心を内蔵した原子炉圧力容
器と、前記原子炉圧力容器が配備されたドライウエルと
、前記ドライウエルを収納した格納容器と、プール水領
域とドライウエル空間とから成る圧力抑制室と、前記ド
ライウエルと前記プール水中とを連通する流路とを備え
た原子炉格納容器において、前記流路の前記プール水へ
の出口よりも高い位置のプール水を同じく低い位置のプ
ール水中に循環させる循環流路を備え、前記循環流路は
少なくとも一部が前記格納容器の外側に通されているこ
とを特徴とした原子炉格納容器である。The sixth means includes a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, a pool water area, and a dry well space. In a nuclear reactor containment vessel, the containment vessel is equipped with a pressure suppression chamber consisting of a pressure suppression chamber, and a flow path that communicates the dry well with the pool water, wherein the pool water at a position higher than the outlet of the flow path to the pool water is connected to the pool water at a lower position. The nuclear reactor containment vessel is characterized in that the reactor containment vessel is provided with a circulation flow path for circulating water in the pool, and at least a portion of the circulation flow path passes through the outside of the containment vessel.
【００２２】第７手段は、第６手段において、前記循環
流路の途中に冷却手段の作用を備えたことを特徴とした
原子炉格納容器である。[0022] A seventh means is a reactor containment vessel according to the sixth means, characterized in that a cooling means is provided in the middle of the circulation flow path.
【００２３】第８手段は、炉心を内蔵した原子炉圧力容
器と、前記原子炉圧力容器が配備されたドライウエルと
、前記ドライウエルを収納した格納容器と、プール水領
域とドライウエル空間とから成る圧力抑制室と、前記ド
ライウエルと前記プール水中とを連通する流路とを備え
た原子炉格納容器において、前記圧力抑制室に蒸気流体
と他の流体との分別収集手段を装備したことを特徴とし
た原子炉格納容器である。[0023] The eighth means includes a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, a pool water area, and a dry well space. In the reactor containment vessel, the reactor containment vessel is equipped with a pressure suppression chamber and a flow path communicating between the dry well and the pool water, wherein the pressure suppression chamber is equipped with means for separating and collecting steam fluid and other fluids. This is the reactor containment vessel that is the main feature.
【００２４】第９手段は、第８手段において、前記格納
容器は少なくとも圧力抑制室のプール水領域が前記プー
ル水と内面において接する鋼製の壁により構成され、前
記鋼製の壁の外周面に対する冷却手段を備えていること
を特徴とした原子炉格納容器である。[0024] According to a ninth means, in the eighth means, the containment vessel is constituted by a steel wall in which at least the pool water region of the pressure suppression chamber is in contact with the pool water on the inner surface, and This is a reactor containment vessel characterized by being equipped with cooling means.
【００２５】第１０手段は、炉心を内蔵した原子炉圧力
容器と、前記原子炉圧力容器が配備されたドライウエル
と、前記ドライウエルを収納した格納容器と、プール水
領域とドライウエル空間とから成る圧力抑制室と、前記
ドライウエルと前記プール水中とを連通する流路とを備
えた原子炉格納容器において、前記プール水の水面上方
に前記プール水の蒸発抑制手段を備えたことを特徴とし
た原子炉格納容器である。The tenth means includes a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, a pool water area, and a dry well space. A nuclear reactor containment vessel comprising a pressure suppression chamber consisting of a pressure suppression chamber and a flow path communicating between the dry well and the pool water, characterized in that the reactor containment vessel is provided with evaporation suppressing means for the pool water above the water surface of the pool water. This is the reactor containment vessel.
【００２６】第１１手段は、第１０手段において、前記
格納容器は少なくとも圧力抑制室のプール水領域が前記
プール水と内面において接する鋼製の壁により構成され
、前記鋼製の壁の外周面に対する冷却手段を備えている
ことを特徴とした原子炉格納容器である。In an eleventh means, in the tenth means, the containment vessel is constituted by a steel wall in which at least the pool water region of the pressure suppression chamber is in contact with the pool water on the inner surface, and This is a reactor containment vessel characterized by being equipped with cooling means.
【００２７】第１２手段は、炉心を内蔵した原子炉圧力
容器が配備されたドライウエルと、圧力抑制プール水を
保有する圧力抑制室と、前記ドライウエルと前記圧力抑
制プール水中を連通するベント管と、前記圧力抑制プー
ル水に接して前記圧力抑制プール水の外周囲を囲う鋼製
の壁と、前記壁の外周面に接して冷却水を内蔵出来る外
周プールとを備えた原子炉格納容器において、前記圧力
抑制室内の圧力抑制プール上方に位置するウエットウエ
ルを、前記圧力抑制プール水の水面と接する領域とそう
でない領域に区画し、前記両領域を前記区画面よりも狭
い面積の流路で連通するとともに、圧力抑制プール水水
面に接しない領域を冷却する手段を備えたことを特徴と
した原子炉格納容器である。[0027] The twelfth means includes a dry well in which a reactor pressure vessel containing a reactor core is provided, a pressure suppression chamber holding pressure suppression pool water, and a vent pipe communicating the dry well and the pressure suppression pool water. and a reactor containment vessel comprising a steel wall that is in contact with the pressure suppression pool water and surrounds the outer periphery of the pressure suppression pool water, and an outer peripheral pool that is in contact with the outer peripheral surface of the wall and can contain cooling water. , a wet well located above the pressure suppression pool in the pressure suppression chamber is divided into an area in contact with the water surface of the pressure suppression pool and an area not in contact with the water surface of the pressure suppression pool, and both areas are formed with a flow path having an area narrower than the partition surface. This reactor containment vessel is characterized by having means for communicating with the pressure suppression pool and for cooling an area not in contact with the water surface of the pressure suppression pool.
【００２８】第１３手段は、第１２手段に記載の原子炉
格納容器において、圧力抑制プール水水面に接しない領
域の下部と圧力抑制プール水中を連通する流路を設けた
ことを特徴とした原子炉格納容器である。A thirteenth means is a nuclear reactor containment vessel according to the twelfth means, characterized in that a flow path is provided that communicates the lower part of the area not in contact with the pressure suppression pool water surface with the pressure suppression pool water. This is the reactor containment vessel.
【００２９】第１４手段は、炉心を内蔵した原子炉圧力
容器が配備されたドライウエルと、圧力抑制プール水を
保有する圧力抑制室と、前記ドライウエルと前記圧力抑
制プール水中を連通するベント管と、前記圧力抑制プー
ル水に接して前記圧力抑制プール水の外周囲を囲う鋼製
の壁と、前記壁の外周面に接して冷却水を内蔵出来る外
周プールとを備えた原子炉格納容器において、前記圧力
抑制プール水水面に、前記圧力抑制プール水よりも飽和
蒸気圧が低く、かつ密度が小さい疎水性物質の層を形成
したことを特徴とした原子炉格納容器である。The fourteenth means includes a dry well in which a reactor pressure vessel containing a reactor core is provided, a pressure suppression chamber holding pressure suppression pool water, and a vent pipe communicating the dry well and the pressure suppression pool water. and a reactor containment vessel comprising a steel wall that is in contact with the pressure suppression pool water and surrounds the outer periphery of the pressure suppression pool water, and an outer peripheral pool that is in contact with the outer peripheral surface of the wall and can contain cooling water. , a nuclear reactor containment vessel characterized in that a layer of a hydrophobic substance having a lower saturated vapor pressure and a lower density than the pressure suppression pool water is formed on the water surface of the pressure suppression pool.
【００３０】第１５手段は、炉心を内蔵した原子炉圧力
容器が配備されたドライウエルと、圧力抑制プール水を
保有する圧力抑制室と、前記ドライウエルと前記圧力抑
制プール水中を連通するベント管と、前記圧力抑制プー
ル水に接して前記圧力抑制プール水の外周囲を囲う鋼製
の壁と、前記壁の外周面に接して冷却水を内蔵出来る外
周プールとを備えた原子炉格納容器において、前記圧力
抑制プール水水面下方にて前記ベント管の出口高さの上
下となる各位置で前記圧力抑制プール水中に開かれたそ
れぞれ少なくとも一つ以上の開口部を有し、前記上下の
各開口部を上下方向に連結して内部に前記圧力抑制プー
ル水が通る対流促進管が前記外周プール内にあることを
特徴とした原子炉格納容器である。The fifteenth means includes a dry well in which a reactor pressure vessel containing a reactor core is provided, a pressure suppression chamber holding pressure suppression pool water, and a vent pipe communicating the dry well and the pressure suppression pool water. and a reactor containment vessel comprising a steel wall that is in contact with the pressure suppression pool water and surrounds the outer periphery of the pressure suppression pool water, and an outer peripheral pool that is in contact with the outer peripheral surface of the wall and can contain cooling water. , at least one or more openings are opened into the pressure suppression pool water at respective positions above and below the outlet height of the vent pipe below the water surface of the pressure suppression pool, and each of the upper and lower openings is provided. The reactor containment vessel is characterized in that a convection promoting pipe is provided in the outer circumferential pool, and the pressure suppression pool water passes through the convection promoting pipe that connects the parts in the vertical direction.
【００３１】第１６手段は、第１５手段において、前記
上方の開口部と前記ベント管の出口との高さの差が、前
記ベント管の出口と前記下方の開口部との高さの差より
大きいことを特徴とした原子炉格納容器である。A sixteenth means is the fifteenth means, wherein the difference in height between the upper opening and the outlet of the vent pipe is greater than the difference in height between the outlet of the vent pipe and the lower opening. It is a reactor containment vessel characterized by its large size.
【００３２】第１７手段は、第１５手段又は第１６手段
において、前記外周プール内に上下に分けて夫々配備さ
れたヘッダ管と、前記上方のヘッダ管と前記下方のヘッ
ダ管とを連通する複数の伝熱管とによって前記対流促進
管を構成したことを特徴とした原子炉格納容器である。[0032] The seventeenth means is the fifteenth means or the sixteenth means, wherein the header pipes are arranged in upper and lower parts in the outer circumferential pool, and a plurality of header pipes that communicate with the upper header pipe and the lower header pipe are provided. The reactor containment vessel is characterized in that the convection promoting tube is constituted by a heat transfer tube.
【００３３】第１８手段は、炉心を内蔵した原子炉圧力
容器が配備されたドライウエルと、圧力抑制プール水を
保有する圧力抑制室と、前記ドライウエルと前記圧力抑
制プール水中を連通するベント管と、前記圧力抑制室の
外周囲を囲う鋼製の壁と、前記圧力抑制プール水に対応
する前記壁の外周面に接して冷却水を内蔵出来る外周プ
ールとを備えた原子炉格納容器において、前記外周プー
ルの冷却水水面よりも高い位置で前記壁に接する他の冷
却水を内蔵できるウエットウエル冷却水プールを前記外
周プールとは独立に備えることを特徴とした原子炉格納
容器である。The eighteenth means includes a dry well in which a reactor pressure vessel containing a reactor core is provided, a pressure suppression chamber holding pressure suppression pool water, and a vent pipe communicating the dry well and the pressure suppression pool water. and a reactor containment vessel comprising a steel wall surrounding the outer periphery of the pressure suppression chamber, and an outer peripheral pool that can contain cooling water and in contact with the outer peripheral surface of the wall corresponding to the pressure suppression pool water, The reactor containment vessel is characterized in that it is provided with a wet well cooling water pool that is capable of containing other cooling water and is in contact with the wall at a position higher than the cooling water level of the outer peripheral pool, independent of the outer peripheral pool.
【００３４】第１９手段は、第１８手段に記載の原子炉
格納容器において、前記ウエットウエル冷却水プールに
対応する前記圧力抑制室内の前記壁にリング状構造物を
備えたことを特徴とした原子炉格納容器である。A nineteenth means is the nuclear reactor containment vessel according to the eighteenth means, characterized in that a ring-shaped structure is provided on the wall in the pressure suppression chamber corresponding to the wet well cooling water pool. This is the reactor containment vessel.
【００３５】第２０手段は、第１２手段又は第１３手段
又は第１４手段において、第１５手段から第１７手段ま
でのいずれか１項に記載の対流促進管を備えたことを特
徴とした原子炉格納容器である。[0035] The twentieth means is a nuclear reactor characterized in that the twelfth means, the thirteenth means, or the fourteenth means is equipped with the convection promoting tube according to any one of the fifteenth means to the seventeenth means. It is a containment vessel.
【００３６】第２１手段は、第１２手段又は第１３手段
又は第１４手段において、前記鋼製の壁に沿って圧力抑
制プール水中にあり、その上端が前記ベント管の出口よ
り高い位置に、その下端がベント管の出口よりも低い位
置に成る高さ関係であり、前記上端と前記ベント管の出
口の高さの差を前記ベント管の出口と前記下端の高さの
差より大きくして配備した対流促進板を備えていること
を特徴とした原子炉格納容器である。[0036] In the twelfth means, the thirteenth means, or the fourteenth means, the twenty-first means is located in the pressure suppression pool water along the steel wall, and the upper end thereof is at a position higher than the outlet of the vent pipe. The height relationship is such that the lower end is at a lower position than the outlet of the vent pipe, and the height difference between the upper end and the outlet of the vent pipe is greater than the difference in height between the outlet of the vent pipe and the lower end. This is a nuclear reactor containment vessel characterized by being equipped with a convection promoting plate.
【００３７】第２２手段は、第１２手段又は第１３手段
又は第１４手段又は第１５手段又は第１６手段又は第１
７手段又は第２０手段又は第２１手段において、第１８
手段に記載のウエットウエル冷却水プール又は第１９手
段に記載のウエットウエル冷却水プールとリング状構造
物を備えたことを特徴とした原子炉格納容器である。第
２３手段は、プール水領域と、その領域に接する気相領
域とから成り、前記プール水領域中に蒸気の吐出口を臨
ませてある圧力抑制室において、前記気相領域に少なく
とも一部分が冷却環境下に配備された他室を前記プール
水の蒸発面積より狭い流路面積の流路を通じて連通して
あることを特徴とした圧力抑制室である。The 22nd means is the 12th means, the 13th means, the 14th means, the 15th means, the 16th means, or the 1st means.
In the 7th means or the 20th means or the 21st means, the 18th means
A nuclear reactor containment vessel characterized by comprising the wet well cooling water pool according to the means or the wet well cooling water pool according to the nineteenth means and a ring-shaped structure. A twenty-third means includes a pool water region and a gas phase region in contact with the pool water region, and in a pressure suppression chamber having a steam discharge port facing into the pool water region, at least a portion of the gas phase region is cooled. The pressure suppression chamber is characterized in that other chambers arranged in the environment are communicated through a channel having a channel area smaller than the evaporation area of the pool water.
【００３８】第２４手段は、プール水領域と、その領域
に接する気相領域とから成り、前記プール水領域中に蒸
気の吐出口を臨ませてある圧力抑制室において、前記プ
ール水の水面上方に前記プール水の蒸発抑制手段を備え
たことを特徴とした圧力抑制室である。The twenty-fourth means is a pressure suppression chamber comprising a pool water region and a gas phase region in contact with the region, and having a steam discharge port facing into the pool water region, above the water surface of the pool water. The pressure suppression chamber is characterized in that it is equipped with means for suppressing evaporation of the pool water.
【００３９】第２５手段は、プール水領域と、その領域
に接する気相領域とから成り、前記プール水領域中に蒸
気の吐出口を臨ませてある圧力抑制室において、前記吐
出口よりも高い位置の前記プール水を同じく低い位置の
プール水中に循環させる循環流路を備え、前記循環流路
は少なくとも一部が前記圧力抑制室の圧力抑制機能が成
されているときの前記圧力抑制室中の前記プール水温度
よりも低温の環境下に通されていることを特徴とした圧
力抑制室である。The twenty-fifth means is a pressure suppression chamber comprising a pool water region and a gas phase region in contact with the region, the pressure suppression chamber having a steam discharge port facing into the pool water region, the pressure suppression chamber having a pressure higher than the discharge port. A circulation flow path is provided for circulating the pool water at a lower position into the pool water at a lower position, and the circulation flow path is at least partially inside the pressure suppression chamber when the pressure suppression function of the pressure suppression chamber is performed. The pressure suppression chamber is characterized by being passed through an environment at a temperature lower than the temperature of the pool water.
【００４０】第２６手段は、原子炉格納容器内の漏洩蒸
気を圧力抑制室内のプール水中に放出して凝縮し、前記
凝縮による前記プール水中の蓄熱を前記原子炉格納容器
外へ排出する方法において、前記圧力抑制室内の不凝縮
性気体と前記プール水からの蒸気との混合流体を前記不
凝縮性気体と前記プール水からの蒸気とに分別し、前記
分別後の蒸気を前記プール水を包含する区画に残存させ
、前記分別後の不凝縮気体を前記区画とは流通自在な他
の区画に収集することを特徴とした原子炉格納容器内の
圧力抑制方法である。A twenty-sixth means is a method in which leaked steam in the reactor containment vessel is discharged into pool water in a pressure suppression chamber and condensed, and heat accumulated in the pool water due to the condensation is discharged to the outside of the reactor containment vessel. , separating a mixed fluid of a non-condensable gas in the pressure suppression chamber and steam from the pool water into the non-condensable gas and steam from the pool water, and the separated steam containing the pool water; This is a method for suppressing pressure in a reactor containment vessel, characterized in that the non-condensable gas after the separation is collected in a compartment other than the compartment that can freely circulate.
【００４１】第２７手段は、原子炉格納容器内の漏洩蒸
気を圧力抑制室内のプール水中に放出して凝縮し、前記
凝縮による前記プール水中の蓄熱を前記原子炉格納容器
外へ排出する方法において、前記プール水の沸騰前にお
いては前記プール水と前記圧力抑制室内気相空間との接
触を断ち、前記プール水の沸騰によって前記プール水か
ら前記圧力抑制室内気相空間への蒸気移行を行うとによ
り前記プール水の蒸発開始を圧力抑制室気相空間の蒸気
分圧の飽和温度から前記圧力抑制室気相空間の全圧力の
飽和温度に変えたことを特徴とした原子炉格納容器内の
圧力抑制方法である。[0041] The twenty-seventh means is a method of releasing leaked steam in the reactor containment vessel into pool water in a pressure suppression chamber and condensing it, and discharging heat accumulated in the pool water due to the condensation to the outside of the reactor containment vessel. , before the pool water boils, the contact between the pool water and the gas phase space of the pressure suppression chamber is cut off, and the boiling of the pool water causes vapor transfer from the pool water to the gas phase space of the pressure suppression chamber. The pressure in the reactor containment vessel is characterized in that the start of evaporation of the pool water is changed from the saturation temperature of the steam partial pressure in the gas phase space of the pressure suppression chamber to the saturation temperature of the total pressure in the gas phase space of the pressure suppression chamber. This is a method of suppression.
【００４２】第２８手段は、原子炉格納容器内の漏洩蒸
気を圧力抑制室内のプール水中に放出して凝縮し、前記
凝縮による前記プール水中の蓄熱を前記原子炉格納容器
外へ排出する方法において、前記圧力抑制室への前記蒸
気の放出位置の高さよりも高い位置の前記プール水の領
域と前記蒸気の放出位置の高さよりも低い位置の前記プ
ール水領域とを連通し、前記連通途中の前記プール水を
冷却して温度依存による密度を高めて前記蒸気の放出位
置の高さよりも高い位置の前記プール水の領域から前記
蒸気の放出位置の高さよりも低い位置の前記プール水領
域への循環駆動力を得ることを特徴とした原子炉格納容
器内の圧力抑制方法である。The twenty-eighth means is a method of releasing leaked steam in the reactor containment vessel into pool water in a pressure suppression chamber and condensing it, and discharging heat accumulated in the pool water due to the condensation to the outside of the reactor containment vessel. , communicating the pool water area at a position higher than the height of the steam release position to the pressure suppression chamber and the pool water area at a position lower than the height of the steam release position; The pool water is cooled to increase its temperature-dependent density so that the pool water is transferred from a region of the pool water at a height higher than the height of the steam release point to a region of the pool water lower than the height of the steam release location. This is a pressure suppression method in a reactor containment vessel characterized by obtaining a circulating driving force.
【００４３】[0043]
【作用】第１手段の作用は、ドライウエルに漏れでた高
温高圧蒸気がドライウエル内の不凝縮性ガスとともに圧
力抑制室のプール水中に圧送されて、蒸気は凝縮され、
不凝縮性ガスはウエットウエルに溜る。蒸気が凝縮する
際にプール水に移行した熱によりプール水は蒸発してウ
エットウエルはその蒸発蒸気と不凝縮性ガスの混合流体
が存在する。他の室は比較的低温であるからその混合流
体が他の室にウエットウエルから入って来ると混合流体
中の蒸気は凝縮して液体と成り圧力は低下し、他の部屋
には蒸気のほとんど無い不凝縮性ガスの領域と成り、ウ
エットウエルは逆にほぼ蒸気だけの領域になり、格納容
器の耐圧を考慮するに比較的圧力の高いウエットウエル
の蒸気圧力を考慮すれば良い状態と成り、プール水の許
容温度を格納容器の耐圧相当の飽和蒸気温度にまで高め
ることが出来、その分だけ圧力抑制プールとその外側と
の間の温度差を大きく出来、放熱能力が高まる。[Operation] The operation of the first means is that the high-temperature, high-pressure steam leaking into the dry well is forced into the pool water of the pressure suppression chamber together with the non-condensable gas in the dry well, and the steam is condensed.
Noncondensable gases accumulate in the wet well. The pool water evaporates due to the heat transferred to the pool water when the steam condenses, and a mixed fluid of the evaporated steam and non-condensable gas exists in the wet well. Since the other chambers are relatively low temperature, when the mixed fluid enters the other chambers from the wet well, the vapor in the mixed fluid condenses and becomes liquid, and the pressure decreases, and most of the vapor is in the other chambers. On the contrary, the wet well becomes an area of almost only steam, which is in good condition as long as the steam pressure of the wet well is relatively high considering the pressure resistance of the containment vessel. The allowable temperature of the pool water can be raised to the saturated steam temperature equivalent to the pressure resistance of the containment vessel, and the temperature difference between the pressure suppression pool and the outside thereof can be increased accordingly, increasing the heat dissipation capacity.
【００４４】第２手段の作用は、第１手段の作用を前記
圧力抑制室内で達成できる。The action of the second means can be achieved within the pressure suppression chamber.
【００４５】第３手段の作用は、第１又は２手段の作用
において、圧力抑制室のプール水領域が伝熱性の良い鋼
製の壁を介して外周プール水に接するから圧力抑制室の
プール水領域から外周プール水への熱伝導効率が良く放
熱能力がより一層高まる。The effect of the third means is that in the effect of the first or second means, the pool water area of the pressure suppression chamber is in contact with the outer peripheral pool water through the steel wall with good heat conductivity, so that the pool water of the pressure suppression chamber is The heat conduction efficiency from the area to the outer pool water is high, further increasing the heat dissipation capacity.
【００４６】第４手段の作用は、ドライウエルに漏れで
た高温高圧蒸気がドライウエル内の不凝縮性ガスととも
に圧力抑制室のプール水中に流路を通って圧送されて、
蒸気は凝縮され、不凝縮性ガスはウエットウエルに溜る
。前記流路の前記プール水への出口よりも高い位置にそ
れより低い位置よりも比較的高温の状態がプール水に生
じる。比較的高温のプール水は循環流路に取水されてそ
の循環流路が外側に通されているから取水されたプール
水は冷却されて密度が高まり、自然に降下して循環流路
の排水口から圧力抑制プール水中に戻されるという循環
力を生じる。その循環により、圧力抑制プール水が動き
放熱が放熱が促進される。The function of the fourth means is that the high-temperature, high-pressure steam leaking into the dry well is forced into the pool water in the pressure suppression chamber through the channel, together with the noncondensable gas in the dry well.
The vapor is condensed and non-condensable gases collect in the wet well. A relatively hotter condition is created in the pool water at a location higher than the outlet of the flow path to the pool water than at a lower location. Relatively high-temperature pool water is taken into the circulation channel, which passes through the circulation channel to the outside, so the pool water that is taken in is cooled, becomes denser, and naturally descends to the drain of the circulation channel. This generates a circulating force that causes the water to flow back into the pressure suppression pool water. Due to the circulation, the pressure suppression pool water moves and heat radiation is promoted.
【００４７】第５手段の作用は、第４手段の作用におい
て、循環流路の途中を冷却手段によりよりよく冷却でき
るので放熱作用がよりよく成される。The effect of the fifth means is that in the effect of the fourth means, the middle of the circulation flow path can be cooled better by the cooling means, so that the heat dissipation effect is better achieved.
【００４８】第６手段は、プール水への蒸気の出口より
も高い位置のプール水を格納容器の外側を経由して同じ
く低い位置のプール水中に循環させることにより、第４
手段と同等の作用が得られる。The sixth means circulates the pool water at a higher position than the steam outlet to the pool water through the outside of the containment vessel into the pool water at a lower position as well.
The same effect as the means can be obtained.
【００４９】第７手段は、第６手段において、前記循環
流路の途中を冷却手段で良く冷却して放熱量を増大し、
第５手段と同等の作用が得られる。[0049] A seventh means, in the sixth means, sufficiently cools a portion of the circulation flow path with a cooling means to increase the amount of heat dissipation;
The same effect as the fifth means can be obtained.
【００５０】第８手段の作用は、ドライウエルに漏れで
た高温高圧蒸気がドライウエル内の不凝縮性ガスととも
に圧力抑制室のプール水中に圧送されて、蒸気は凝縮さ
れ、不凝縮性ガスはウエットウエルに溜る。蒸気が凝縮
する際にプール水に移行した熱によりプール水は蒸発し
てウエットウエルはその蒸発蒸気と不凝縮性ガスの混合
流体が存在する。前記混合流体は蒸気流体と他の流体と
に分別収集されて格納容器の耐圧上蒸気圧力だけを考慮
すれば良い状況を作り、圧力抑制プール水の許容温度を
格納容器耐圧の飽和蒸気温度に高め得る作用を得られる
。このために圧力抑制プールと外側との温度差を大きく
して放熱効果を向上出来る。The operation of the eighth means is that the high-temperature, high-pressure steam leaking into the dry well is pumped into the pool water of the pressure suppression chamber together with the non-condensable gas in the dry well, the steam is condensed, and the non-condensable gas is It collects in the wet well. When the steam condenses, the pool water evaporates due to the heat transferred to the pool water, and a mixed fluid of the evaporated steam and non-condensable gas exists in the wet well. The mixed fluid is collected separately into steam fluid and other fluids, creating a situation in which only the steam pressure on the pressure resistance of the containment vessel needs to be considered, and increasing the permissible temperature of the pressure suppression pool water to the saturated steam temperature of the pressure resistance of the containment vessel. You can get the effect you want. For this reason, the temperature difference between the pressure suppression pool and the outside can be increased to improve the heat dissipation effect.
【００５１】第９手段の作用は、第８手段の作用におい
て、圧力抑制プールが伝熱性の良い鋼製の壁を介して冷
却手段に冷却されるから温度差がより大きくなり、放熱
効果がより一層良くなる。The effect of the ninth means is that in the effect of the eighth means, the pressure suppression pool is cooled by the cooling means through the steel wall with good heat conductivity, so the temperature difference becomes larger and the heat dissipation effect is further improved. It gets even better.
【００５２】第１０手段の作用は、ドライウエルに漏れ
でた高温高圧蒸気がドライウエル内の不凝縮性ガスとと
もに圧力抑制室のプール水中に圧送されて、蒸気は凝縮
され、不凝縮性ガスはウエットウエルに溜る。この凝縮
により圧力抑制プール水は昇温するものの蒸発抑制手段
により蒸発が抑制されるから、従来はウエットウエルの
蒸気分圧の飽和温度から始まるプール水の蒸発を、ウエ
ットウエルの全圧力の飽和温度から始まる。このために
、同じウエットウエル圧力下においても、圧力抑制プー
ル水温度をより高い温度で存在させることが出来る。
このために、圧力抑制プールと原子炉格納容器外との温
度差を大きくして放熱効果を向上できる。第１１手段の
作用は、第１０手段の作用において、圧力抑制プールが
伝熱性の良い鋼製の壁を介して冷却手段に冷却されるか
ら温度差がより大きくなり、放熱効果がより一層良くな
る。The action of the tenth means is that the high-temperature, high-pressure steam leaking into the dry well is pumped into the pool water of the pressure suppression chamber together with the non-condensable gas in the dry well, the steam is condensed, and the non-condensable gas is It collects in the wet well. This condensation raises the temperature of the pressure suppression pool water, but the evaporation is suppressed by the evaporation suppression means. Conventionally, the evaporation of pool water starts from the saturation temperature of the vapor partial pressure of the wet well, but the evaporation of the pool water starts from the saturation temperature of the total pressure of the wet well. start from. For this reason, even under the same wet well pressure, the pressure suppression pool water temperature can be maintained at a higher temperature. For this reason, the temperature difference between the pressure suppression pool and the outside of the reactor containment vessel can be increased to improve the heat dissipation effect. The effect of the eleventh means is that in the effect of the tenth means, the pressure suppression pool is cooled by the cooling means through the steel wall with good heat conductivity, so the temperature difference becomes larger and the heat dissipation effect is further improved. .
【００５３】第１２手段の作用は、ドライウエルに漏れ
でた高温高圧蒸気がドライウエル内の不凝縮性ガスとと
もに圧力抑制室のプール水中に圧送されて、蒸気は凝縮
され、不凝縮性ガスはウエットウエルに溜る。蒸気が凝
縮する際にプール水に移行した熱によりプール水は蒸発
してプール水に面した領域はその蒸発蒸気と不凝縮性ガ
スの混合流体が存在する。他の領域は比較的低温である
からその混合流体が他の領域に入って来ると混合流体中
の蒸気は凝縮して液体と成り圧力は低下し、他の部屋に
は蒸気のほとんど無い不凝縮性ガスの領域と成り、プー
ル水に面した領域は逆にほぼ蒸気だけの領域になり、格
納容器の耐圧を考慮するに比較的圧力の高いウエットウ
エルの蒸気圧力を考慮すれば良い状態と成り、プール水
の許容温度を格納容器の耐圧相当の飽和蒸気温度にまで
高めることが出来、その分だけ圧力抑制プールとその外
側との間の温度差を大きく出来、放熱能力が高まる。そ
して、両領域間は狭い流路で連通されているから、他の
領域への混合流体の侵入は徐々に行われて混合流体中の
蒸気に対する凝縮が間に合わなくなることを抑制でき、
確実に不凝縮性ガスと蒸気との分別収集が可能となる。The action of the twelfth means is that the high-temperature, high-pressure steam leaking into the dry well is pumped into the pool water of the pressure suppression chamber together with the non-condensable gas in the dry well, the steam is condensed, and the non-condensable gas is It collects in the wet well. The pool water evaporates due to the heat transferred to the pool water when the steam condenses, and a mixed fluid of the evaporated steam and non-condensable gas exists in the region facing the pool water. Other areas are relatively low-temperature, so when the mixed fluid enters another area, the vapor in the mixed fluid condenses and becomes liquid, reducing the pressure, while other rooms are noncondensable with almost no vapor. On the other hand, the area facing the pool water becomes an area containing almost only steam, which is a good condition if you take into account the steam pressure of the wet well, which is relatively high pressure when considering the pressure resistance of the containment vessel. The allowable temperature of the pool water can be raised to the saturated steam temperature equivalent to the pressure resistance of the containment vessel, and the temperature difference between the pressure suppression pool and the outside thereof can be increased accordingly, increasing the heat dissipation capacity. Since the two regions are communicated with each other by a narrow flow path, the mixed fluid gradually enters the other region, and it is possible to prevent the steam in the mixed fluid from being condensed in time.
It is possible to reliably separate and collect noncondensable gas and steam.
【００５４】第１３手段の作用は、第１２手段の作用を
、圧力抑制プール水水面に接しない領域から圧力抑制プ
ール水中へ凝縮した流体を戻して不凝縮性ガスの充満度
合いを高めて確実に成すようにできる。The action of the thirteenth means is to ensure the action of the twelfth means by returning the condensed fluid into the pressure suppression pool water from an area not in contact with the pressure suppression pool water surface to increase the degree of filling with noncondensable gas. I can make it happen.
【００５５】第１４手段の作用は、ドライウエルに漏れ
でた高温高圧蒸気がドライウエル内の不凝縮性ガスとと
もに圧力抑制室のプール水中に圧送されて、蒸気は凝縮
され、不凝縮性ガスはウエットウエルに溜る。この凝縮
により圧力抑制プール水は昇温するものの蒸発が、プー
ル水面に浮遊した疎水性物質の層が水よりも飽和蒸気圧
が低いので、抑制されるから、従来はウエットウエルの
蒸気分圧の飽和温度から始まるプール水の蒸発を、ウエ
ットウエルの全圧力の飽和温度から始まる。このために
、同じウエットウエル圧力下においても、圧力抑制プー
ル水温度をより高い温度で存在させることが出来る。
このために、圧力抑制プールと原子炉格納容器外との温
度差を大きくして放熱効果を向上できる。The function of the fourteenth means is that the high-temperature, high-pressure steam leaking into the dry well is pumped into the pool water of the pressure suppression chamber together with the non-condensable gas in the dry well, the steam is condensed, and the non-condensable gas is It collects in the wet well. This condensation raises the temperature of the pressure suppression pool water, but evaporation is suppressed because the layer of hydrophobic substances suspended on the pool water surface has a lower saturated vapor pressure than the water. The evaporation of the pool water starts from the saturation temperature and the saturation temperature of the total pressure of the wetwell. For this reason, even under the same wet well pressure, the pressure suppression pool water temperature can be maintained at a higher temperature. For this reason, the temperature difference between the pressure suppression pool and the outside of the reactor containment vessel can be increased to improve the heat dissipation effect.
【００５６】第１５手段の作用は、ドライウエルに漏れ
でた高温高圧蒸気がドライウエル内の不凝縮性ガスとと
もに圧力抑制室のプール水中に圧送されて、蒸気は凝縮
され、不凝縮性ガスはウエットウエルに溜る。この凝縮
により圧力抑制プール水は昇温してベント管出口よりも
上層に溜る。その高温のプール水は対流促進管を通って
外周プールにより冷却され、その冷却により対流促進管
ないのプール水の密度が大きくなり、下方降下してベン
ト管出口よりも下層の圧力抑制プール内に戻るという循
環流が生じる。この様な循環により冷却が促進されて、
放熱効果が上がる。The action of the fifteenth means is that the high-temperature, high-pressure steam leaking into the dry well is pumped into the pool water in the pressure suppression chamber together with the non-condensable gas in the dry well, the steam is condensed, and the non-condensable gas is It collects in the wet well. This condensation causes the pressure suppression pool water to rise in temperature and accumulate in a layer above the vent pipe outlet. The high-temperature pool water passes through the convection tube and is cooled by the outer pool, and as a result of this cooling, the density of the pool water outside the convection tube increases, and it descends into the pressure suppression pool below the vent tube outlet. A circular flow of return occurs. This circulation promotes cooling,
Heat dissipation effect increases.
【００５７】第１６手段の作用は、第１５手段の作用に
おいて、対流促進管の上方の開口部とベント管の出口と
の高さの差を、ベント管の出口と対流促進管の下方の開
口部との高さの差より大きいから、循環が維持できる密
度差が長期に確実に維持できる作用が得られる。The action of the sixteenth means is such that, in the action of the fifteenth means, the difference in height between the upper opening of the convection promoting tube and the outlet of the vent pipe is reduced to the height difference between the outlet of the vent pipe and the lower opening of the convection promoting tube. Since the difference in height is greater than the difference in height between the two parts, the difference in density that allows circulation to be maintained can be maintained reliably for a long period of time.
【００５８】第１７手段の作用は、第１５手段の作用又
は第１６手段の作用において、圧力抑制プール水が、上
方のヘッダ管から複数の伝熱管に分流して再度下方のヘ
ッダ管に合流させられるから、放熱面積が広い割には格
納容器を貫通する流路が少なくてすみ、格納容器の健全
性と放熱の向上とを両立できる。The action of the seventeenth means is such that, in the action of the fifteenth means or the action of the sixteenth means, the pressure suppression pool water is divided from the upper header pipe to a plurality of heat transfer tubes and rejoined to the lower header pipe. Therefore, although the heat dissipation area is large, the number of flow paths passing through the containment vessel is small, and the integrity of the containment vessel and improvement in heat dissipation can be achieved at the same time.
【００５９】第１８手段の作用は、ドライウエルに漏れ
でた高温高圧蒸気がドライウエル内の不凝縮性ガスとと
もに圧力抑制室のプール水中に圧送されて、蒸気は凝縮
され、不凝縮性ガスはウエットウエルに溜る。この凝縮
により圧力抑制プール水は昇温して蒸発し、ウエットウ
エルに蒸気も溜る。この蒸気はウエットウエル冷却水プ
ールにより冷却されて凝縮される。又外周プールにより
圧力抑制プールは冷却される。これら両者の冷却により
、格納容器内の圧力が抑制される。ウエットウエル冷却
水プールは外周プールとは独立しているから、ウエット
ウエル冷却水プールのプール水の水頭が外周プールのプ
ール水の水頭と累積して格納容器の同一個所に加わるこ
とが無いから、水冷による冷却効果の良さを維持しなが
らも、格納容器の健全性を維持できる。The action of the eighteenth means is that the high-temperature, high-pressure steam leaking into the dry well is pumped into the pool water of the pressure suppression chamber together with the non-condensable gas in the dry well, the steam is condensed, and the non-condensable gas is It collects in the wet well. This condensation causes the pressure suppression pool water to rise in temperature and evaporate, and steam also accumulates in the wet well. This steam is cooled and condensed by a wet well cooling water pool. The pressure suppression pool is also cooled by the outer peripheral pool. By cooling both of them, the pressure inside the containment vessel is suppressed. Since the wet well cooling water pool is independent from the outer pool, the water head of the wet well cooling water pool will not accumulate with the pool water head of the outer pool and will not be added to the same part of the containment vessel. The integrity of the containment vessel can be maintained while maintaining the good cooling effect of water cooling.
【００６０】第１９手段の作用は、第１８手段の作用に
記載の原子炉格納容器において、ウエットウエル冷却水
プールに対応する圧力抑制室内の壁をリング状構造物で
補強してより一層の格納容器の健全性を達成できるし、
そのリング状構造物が凝縮面積を拡大するので冷却効果
がより高まる。The effect of the nineteenth means is that in the reactor containment vessel described in the effect of the eighteenth means, the wall of the pressure suppression chamber corresponding to the wet well cooling water pool is reinforced with a ring-shaped structure to further enhance containment. Container integrity can be achieved and
Since the ring-shaped structure expands the condensation area, the cooling effect is further enhanced.
【００６１】第２０手段の作用は、第１２手段の作用又
は第１３手段の作用又は第１４手段の作用において、第
１５手段の作用から第１７手段の作用までのいずれか１
手段の作用を重畳させて放熱効果を向上できる。The action of the twentieth means is any one of the actions of the fifteenth means to the seventeenth means in the action of the twelfth means, the action of the thirteenth means, or the action of the fourteenth means.
The heat dissipation effect can be improved by superimposing the effects of the means.
【００６２】第２１手段の作用は、第１２手段の作用又
は第１３手段の作用又は第１４手段の作用において、対
流促進板でプール水の対流領域を拡大して鋼製の壁から
の放熱を向上させ、放熱作用の向上が成される。The action of the twenty-first means is that, in the action of the twelfth means, the action of the thirteenth means, or the action of the fourteenth means, the convection area of the pool water is expanded by the convection promoting plate, thereby increasing heat dissipation from the steel wall. This improves the heat dissipation effect.
【００６３】第２２手段の作用は、第１２手段の作用又
は第１３手段の作用又は第１４手段又は第１５手段の作
用又は第１６手段の作用又は第１７手段の作用又は第２
０手段の作用又は第２１手段の作用において、ウエット
ウエル冷却水プールでウエットウエルも水冷して冷却効
果を高めるとともに水冷によるプール水の荷重分布を外
周プールとは分散して格納容器の健全性を維持する作用
が加わる、又はそれに加えて、リング状構造物で格納容
器を補強してより健全性を高め、さらにはリング状構造
物が凝縮面を広げる作用を成して冷却効果をより高める
作用が加わる。第２３手段の作用は、プール水領域に蒸
気が吐出されると、蒸気は凝縮されてプール水が昇温し
、プール水が蒸発して気相領域に立ちこめて冷却環境下
の他室にも狭い流路を通って徐々に入る。この他室では
気相領域よりも低温であるから、蒸気は凝縮されて不凝
縮性ガスが充満し、気相領域は蒸気で充満する。この様
にして不凝縮性ガスと蒸気とを分別して収集し、プール
水の許容温度を圧力抑制室の耐圧の飽和蒸気温度とする
ことにより、プールとその外側との温度差を大きくして
外側への放熱量を大きく出来る。The action of the 22nd means is the action of the 12th means, or the action of the 13th means, or the action of the 14th means, or the action of the 15th means, or the action of the 16th means, or the action of the 17th means, or the action of the 17th means, or
In the action of the 0th means or the 21st means, the wet well is also water-cooled in the wet well cooling water pool to enhance the cooling effect, and the load distribution of the pool water due to water cooling is dispersed from that of the outer peripheral pool to improve the integrity of the containment vessel. In addition to this, the ring-shaped structure reinforces the containment vessel to further improve its integrity, and the ring-shaped structure also acts to widen the condensation surface to further enhance the cooling effect. is added. The function of the twenty-third means is that when steam is discharged into the pool water area, the steam is condensed and the temperature of the pool water rises, and the pool water evaporates and accumulates in the gas phase area, which also spreads to other rooms in the cooling environment. It enters gradually through a narrow channel. Since the other chamber is at a lower temperature than the gas phase region, the steam is condensed and filled with non-condensable gas, and the gas phase region is filled with steam. In this way, non-condensable gas and steam are separated and collected, and the allowable temperature of the pool water is set to the pressure-resistant saturated steam temperature of the pressure suppression chamber, thereby increasing the temperature difference between the pool and the outside. The amount of heat dissipated to can be increased.
【００６４】第２４手段の作用は、プール水領域に蒸気
が吐出されると、蒸気は凝縮されてプール水が昇温し、
蒸発しようとするがその蒸発は蒸発抑制手段により抑制
され、従来気相の蒸気分圧の飽和温度から始まる蒸発を
、気相の全圧力の飽和温度から始まるように変更できる
ので、同じ圧力下においてもプール水温度をより高い温
度で存在できるように出来る。このために、プールとそ
の外側との温度差を大きくして外側への放熱量を大きく
出来る。The function of the twenty-fourth means is that when steam is discharged into the pool water area, the steam is condensed and the temperature of the pool water increases;
Although the evaporation tends to evaporate, it is suppressed by the evaporation suppressing means, and the evaporation that conventionally starts at the saturation temperature of the vapor partial pressure of the gas phase can be changed to start from the saturation temperature of the total pressure of the gas phase. It can also allow the pool water temperature to exist at a higher temperature. For this reason, it is possible to increase the temperature difference between the pool and the outside, thereby increasing the amount of heat radiated to the outside.
【００６５】第２５手段の作用は、プール水領域に蒸気
が吐出されると、蒸気は凝縮されてプール水が昇温し、
昇温した上層のプール水が循環流路で低温の環境にとお
されて放熱され密度が大きくなって降下し、低い位置の
低温のプール水中に循環する作用を成し、圧力抑制室か
ら外部低温環境下への放熱が成される。The function of the twenty-fifth means is that when steam is discharged into the pool water area, the steam is condensed and the temperature of the pool water increases;
The heated upper layer pool water passes through the circulation channel to a low temperature environment, radiates heat, increases its density, and falls, circulating into the low temperature pool water at a lower position, and from the pressure suppression chamber to the external low temperature environment. Heat is dissipated to the environment.
【００６６】第２６の手段によれば、冷却材喪失事故に
よる圧力抑制室内の不凝縮性気体とプール水からの蒸気
との混合流体を前記不凝縮性気体と前記プール水からの
蒸気とに分別してプール水許容温度を格納容器耐圧の飽
和蒸気温度とし、プール水温度と格納容器外温度との差
を大きくする作用が得られる。その大きな温度差により
放熱効果が向上する。According to the twenty-sixth means, a mixed fluid of non-condensable gas and steam from the pool water in the pressure suppression chamber due to a loss of coolant accident is separated into the non-condensable gas and the steam from the pool water. Separately, the allowable temperature of the pool water is set to the saturated steam temperature of the containment vessel pressure resistance, and an effect of increasing the difference between the pool water temperature and the outside temperature of the containment vessel can be obtained. The large temperature difference improves the heat dissipation effect.
【００６７】第２７の手段によれば、冷却喪失事故によ
り昇温したプール水から気相空間への蒸発作用を抑制し
て、プール水の蒸発を気相の全圧力の飽和温度から始ま
るようにし、プール水を高い温度に存在させる。このこ
とにより、プール水温度と格納容器外温度との差を大き
くする作用が得られる。その大きな温度差により放熱効
果が向上する。According to the twenty-seventh means, the evaporation effect from the pool water whose temperature has increased due to a loss of cooling accident into the gas phase space is suppressed, and the evaporation of the pool water starts from the saturation temperature of the total pressure of the gas phase. , causing the pool water to be at a higher temperature. This provides the effect of increasing the difference between the pool water temperature and the temperature outside the containment vessel. The large temperature difference improves the heat dissipation effect.
【００６８】第２８の手段によれば、冷却喪失事故によ
り昇温した上層のプール水と下層のプール水中を連通す
る流路内のプール水が冷却されて密度が高められ、降下
することにより循環力が得られ、昇温した上層のプール
水が下層のプール水中へ循環し、プール水中の温度の均
等化を成し、プール水中での蓄熱領域の拡大と放熱効率
の高い領域の拡大とが成される。そのプール水は循環途
中においても冷却されるから循環途中の放熱も有って、
全体として放熱効果が良くなる。According to the twenty-eighth means, the pool water in the flow path that communicates the upper pool water and the lower pool water, whose temperature has increased due to a cooling loss accident, is cooled, its density is increased, and the water is circulated by descending. The heated upper pool water circulates to the lower pool water, equalizing the temperature in the pool water, expanding the heat storage area in the pool water and expanding the area with high heat dissipation efficiency. will be accomplished. Since the pool water is cooled even during circulation, there is also heat dissipation during circulation.
Overall, the heat dissipation effect is improved.
【００６９】[0069]
【実施例】原子炉格納容器の圧力抑制室の許容温度は、
次のように定まる。原子炉格納容器の圧力バウダリーで
ある容器壁に接するウエットウエルの圧力はウエットウ
エル内の不凝縮気体分圧と蒸気分圧の和である。事故時
における不凝縮性気体分圧の最高値は通常運転時に原子
炉格納容器内にある全ての不凝縮性気体がウエットウエ
ルに蓄積されるので原子炉格納容器の全気相体積とウエ
ットウエル体積の比から定まるものである。また、蒸気
分圧は圧力抑制プール表面温度の飽和蒸気圧として定ま
る。事故時において、この両圧力の和であるウエットウ
エルの圧力が容器の耐圧以下となるように、すなわち蒸
気分圧が容器の耐圧と不凝縮性気体分圧の差の圧力以下
となるように、圧力抑制プール温度を制限する必要が有
り、これが許容温度になる。[Example] The allowable temperature of the pressure suppression chamber of the reactor containment vessel is
It is determined as follows. The pressure of the wet well in contact with the vessel wall, which is the pressure boundary of the reactor containment vessel, is the sum of the non-condensable gas partial pressure and the steam partial pressure within the wet well. The maximum value of the non-condensable gas partial pressure at the time of the accident is determined by the total gas phase volume of the reactor containment vessel and the wet well volume, since all the non-condensable gases in the reactor containment vessel during normal operation are accumulated in the wet well. It is determined from the ratio of Further, the steam partial pressure is determined as the saturated steam pressure at the pressure suppression pool surface temperature. In the event of an accident, the pressure in the wet well, which is the sum of both pressures, will be below the container's proof pressure, that is, the steam partial pressure will be below the pressure difference between the container's proof pressure and the non-condensable gas partial pressure. It is necessary to limit the pressure suppression pool temperature and this becomes the permissible temperature.
【００７０】本発明の基本的実施例は大きく分けて四例
である。The basic embodiments of the present invention can be roughly divided into four types.
【００７１】第１の基本的実施例では、以下の動作によ
り圧力抑制室の許容温度を上昇させて外周囲との温度差
を大きくし、大きな温度差により大量の熱を外周囲に放
熱作用を得る。即ち、事故時に原子炉格納容器のドライ
ウエルの不凝縮性気体は原子炉容器から放出される蒸気
に押し出されかつ同伴されてベント管から圧力抑制プー
ルに流入する。この時不凝縮性気体は、まず圧力抑制プ
ール表面に接する空間（以下第１空間と称する）に蓄積
しその領域の圧力を上昇させた後、圧力差に基づいて、
区画された別の空間（以下第２空間と称する）に流入す
る。その後、ベント管を通して圧力抑制プールに蒸気が
流入しプール中で凝縮する結果、圧力抑制プールの水温
が上昇し、第１空間の蒸気分圧が上昇し全圧力も上昇す
る。第１空間内では気相の循環・混合が制限されていな
いので、不凝縮性気体と蒸気が均一に混合される。この
気相は第２空間との圧力差により、第１空間から第２空
間に流入する。第２空間は冷却されており、前記の作用
により不凝縮性気体を伴って流入してきた蒸気の一部あ
るいは全部を凝縮する結果、第２空間の圧力は、第１空
間の圧力より低くなる。これにより、再び第１空間から
不凝縮性気体を伴った蒸気が第２空間に流入する。この
動作が繰り返されることによって、ウエットウエル内の
不凝縮性気体は全て第２空間に蓄積される。第２空間か
ら第１空間への気相の戻りは制限されているため、第１
空間は、蒸気のみが満たされ該空間の圧力としては、蒸
気圧力だけを考慮すれば良い状態になる。この時第２空
間で必要とされる冷却量は、両空間をつなぐ流路を通っ
て流入する蒸気を第１空間での温度より低くするための
量であり、大きな量を必要としない。また、ウエットウ
エルを区画する方法は、上下方向に区画するなどにより
、原子炉格納容器の大きさに影響を与えることはない。
以上の動作の結果、圧力抑制プールの許容温度としては
、容器耐圧の飽和蒸気温度とする作用を得る。これによ
り、原子炉格納容器壁の板厚を変えること無く同一の圧
力容器耐圧条件下で、許容される圧力抑制プール水温を
上昇させることができ、ひいては圧力抑制プールと外周
プール間の温度差を増大し、放熱特性を向上させる作用
を得る。この結果、原子炉格納容器形状が同じであって
もより大出力のプラントに適用が可能となる。In the first basic embodiment, the allowable temperature of the pressure suppression chamber is increased by the following operations to increase the temperature difference with the outside surroundings, and the large temperature difference causes a large amount of heat to be radiated to the outside surroundings. obtain. That is, in the event of an accident, non-condensable gas in the dry well of the reactor containment vessel is pushed out and entrained by the steam released from the reactor vessel and flows into the pressure suppression pool from the vent pipe. At this time, the non-condensable gas first accumulates in the space in contact with the pressure suppression pool surface (hereinafter referred to as the first space) and increases the pressure in that area, and then, based on the pressure difference,
It flows into another partitioned space (hereinafter referred to as a second space). Thereafter, steam flows into the pressure suppression pool through the vent pipe and is condensed in the pool, so that the water temperature in the pressure suppression pool increases, the steam partial pressure in the first space increases, and the total pressure also increases. Since circulation and mixing of the gas phase is not restricted within the first space, non-condensable gas and steam are mixed uniformly. This gas phase flows from the first space into the second space due to the pressure difference with the second space. The second space is cooled, and as a result of the above-mentioned action condensing some or all of the steam that has flowed in with non-condensable gases, the pressure in the second space becomes lower than the pressure in the first space. As a result, steam accompanied by non-condensable gas flows from the first space into the second space again. By repeating this operation, all the non-condensable gas in the wet well is accumulated in the second space. Since the return of the gas phase from the second space to the first space is restricted,
The space is filled only with steam, and the pressure in the space requires only the steam pressure to be considered. The amount of cooling required in the second space at this time is the amount to lower the temperature of the steam flowing in through the flow path connecting both spaces to a temperature lower than that in the first space, and does not require a large amount. Furthermore, the method of dividing the wet well, such as vertically dividing it, does not affect the size of the reactor containment vessel. As a result of the above operations, the allowable temperature of the pressure suppression pool is set to the saturated steam temperature of the container pressure. As a result, the allowable pressure suppression pool water temperature can be increased under the same pressure vessel pressure resistance conditions without changing the thickness of the reactor containment vessel wall, and the temperature difference between the pressure suppression pool and the peripheral pool can be reduced. It has the effect of increasing heat dissipation characteristics. As a result, even if the reactor containment vessel shape is the same, it can be applied to a plant with higher output.
【００７２】第２の基本的実施例では、以下の動作によ
り圧力抑制室の温度を上昇させて外周囲との温度差を大
きくし、大きな温度差により大量の熱を外周囲に放熱作
用を得る。即ち、圧力抑制プール表面に、例えばシリコ
ンオイルやスピンドルオイルのような、飽和蒸気圧が低
く、水より密度が小さい疎水性物質の層を形成させると
、疎水性物質の層でプール水とウエットウエルは隔離さ
れた状態になる。疎水性物質の温度は圧力抑制プール表
面の水温に等しくなるが、飽和蒸気圧が低いため温度上
昇によるウエットウエルの圧力増加は小さい。その内、
圧力抑制プールの温度が上昇し、ウエットウエルの圧力
が低く保たれているので、圧力抑制プールの水が沸騰を
始める。圧力抑制プールの沸騰で発生した蒸気は表面の
疎水性物質の層を通過しウエットウエルに流入し圧力を
上昇させる。ただし、ウエットウエルはプール表面とは
隔離されているため湿度が低く過熱蒸気（温度が蒸気分
圧に対する飽和温度より高い）の状態となる。そして、
ウエットウエルの全圧力（不凝縮性気体分圧と蒸気分圧
の和）が圧力抑制プールの水温の飽和圧力になると圧力
抑制プールの沸騰が停止する。この現象が繰り返される
わけである。すなわち、プール表面に疎水性物質の層を
形成させたことにより、従来はウエットウエルの蒸気分
圧の飽和温度からはじまるプール水の蒸発を、ウエット
ウエルの全圧力の飽和温度から始まるようにすることが
できる。言い替えれば、同じウエットウエル圧力下にお
いても、圧力抑制プール水温度をより高い温度で存在で
きるようにすることができる。ウエットウエルを冷却し
た場合、前述の手段においてウエットウエルを区画する
構造壁の部分を疎水性物質によって代用していると考え
ることもできる。以上の理由により本手段では、ウエッ
トウエル内の許容される蒸気分圧が同じ（容器の耐圧が
同じ）でも許容される圧力抑制プール水温を上昇させる
ことができ、ひいては圧力抑制プールと外周プール間の
温度差を増大し、放熱特性を向上させる作用を得る。こ
の結果、原子炉格納容器形状が同じであってもより大出
力のプラントに適用が可能となる。In the second basic embodiment, the temperature of the pressure suppression chamber is increased by the following operations to increase the temperature difference with the outside surroundings, and the large temperature difference causes a large amount of heat to be radiated to the outside surroundings. . In other words, if a layer of a hydrophobic substance such as silicone oil or spindle oil, which has a low saturated vapor pressure and has a lower density than water, is formed on the pressure suppression pool surface, the layer of hydrophobic substance will separate the pool water from the wet well. becomes isolated. The temperature of the hydrophobic substance is equal to the water temperature on the surface of the pressure suppression pool, but since the saturated vapor pressure is low, the increase in pressure in the wet well due to temperature rise is small. Among them,
As the temperature of the suppression pool increases and the pressure in the wet well remains low, the water in the suppression pool begins to boil. The steam generated by the boiling of the pressure suppression pool passes through the layer of hydrophobic material on the surface and flows into the wet well, increasing the pressure. However, since the wet well is isolated from the pool surface, the humidity is low and the wet well is in a state of superheated steam (temperature higher than saturation temperature with respect to steam partial pressure). and,
When the total pressure in the wet well (the sum of the noncondensable gas partial pressure and the steam partial pressure) reaches the saturation pressure of the water temperature in the pressure suppression pool, boiling in the pressure suppression pool stops. This phenomenon is repeated. In other words, by forming a layer of hydrophobic material on the pool surface, the evaporation of pool water, which conventionally starts at the saturation temperature of the vapor partial pressure of the wet well, can be made to start at the saturation temperature of the total pressure of the wet well. Can be done. In other words, even under the same wet well pressure, the pressure suppression pool water temperature can be allowed to exist at a higher temperature. When the wet well is cooled, it can be considered that the portion of the structural wall that partitions the wet well is replaced by a hydrophobic substance in the above-described means. For the above reasons, with this method, it is possible to increase the allowable pressure suppression pool water temperature even if the allowable steam partial pressure in the wet well is the same (the pressure resistance of the container is the same), and as a result, it is possible to increase the allowable pressure suppression pool water temperature between the pressure suppression pool and the peripheral pool. This has the effect of increasing the temperature difference between and improving heat dissipation characteristics. As a result, even if the reactor containment vessel shape is the same, it can be applied to a plant with higher output.
【００７３】第３の基本的実施例では、以下の動作によ
り原子炉格納容器からの放熱量を大きくしている。即ち
、冷却材喪失時に圧力容器からドライウエルへ放出され
た蒸気は、ベント管を通して圧力抑制プール内に導かれ
プール水中で凝縮する。これにより、ベント管出口より
も上部の圧力抑制プール水温が上昇し、ベント管出口に
おける蒸気凝縮による加熱で形成されるプール内の対流
によって、該領域の温度は一様な高温状態となる。一方
この時点では、ベント管出口より下部のプール水温は上
昇せず、ベント管出口の高さに温度成層が形成される。
この時、本手段の対流促進管の上下端間における圧力抑
制プールと対流促進管の密度状態を考えてみる。ベント
管出口より上方の圧力抑制プールは相対的に高温であり
密度は小さく、対流促進管側は相対的に低温で密度が大
きい状態である。この結果、考慮している区間の下端に
おける水頭（密度と高さの積：ρｇｈ）は、対流促進管
側が大きいため対流促進管内を流下して圧力抑制プール
内に流入する循環が形成される。これにより、圧力抑制
プール上方の高温水が対流促進管の上部に流入するが、
対流促進管はより低温の外周プール中に浸されているた
め管壁を通して放熱が起こり、徐々に低温となって対流
促進管内を流下する。この作用により、ベント管出口よ
り上方では常に対流促進管側の密度ひいては水頭が大き
い状態が維持され、対流促進管を下向きに流れる循環の
駆動力が形成されている。一方ベント管出口より下側の
区間では、循環により対流促進管側がまづ高温となるた
め上記の循環の駆動力を打ち消す方向の密度（水頭）状
態となるが、対流促進管の下端の位置を適正に設定する
（すなわち、対流促進管の下端の位置を上方で形成され
た下向きの駆動力を完全に打ち消すことがない位置とす
る）ことにより対流促進管を下向きに流れる循環を維持
しつつ、かつベント管出口より下側の領域に相対的に高
温の水を流入させることができる。この作用でベント管
出口より下の領域に流入した温水が該領域の水温を上昇
させ、このことがベント管出口より下側の領域において
形成される循環の駆動力を打ち消す方向の密度（水頭）
状態を解消し、循環を促進させる。以上の作用の繰返し
により、ベント管出口より下側の領域の水温も継続的に
上昇させる作用を得る。この時、ベント管出口より下方
の領域の水温は、対流促進管下端から流入する水温にほ
ぼ等しくなるので、外周プール水温より低くなることは
ない。これにより、圧力抑制プールのベント管出口より
下方の低温領域に相対的に高温のプール水を恒常的に循
環させ、炉心からの熱を吸収する領域を増大させるとと
もに、外周プールへの放熱に関する伝熱面積を高温とな
る圧力抑制プール領域に対応した原子炉格納容器壁だけ
ではなく対流促進管壁も伝熱面として利用できる。対流
促進管は、常識的に原子炉格納容器直径より小さいので
、原子炉格納容器耐圧に影響を与えることなく任意に設
置することができるので、原子炉格納容器寸法・原子炉
格納容器耐圧を変更することなく伝熱面積を増大させる
ことができ、ひいては放熱量を増大させる作用を得る。
この結果、原子炉格納容器の主要寸法などが同じであっ
てもより大出力のプラントに適用が可能となる。In the third basic embodiment, the amount of heat released from the reactor containment vessel is increased by the following operation. That is, the steam released from the pressure vessel into the drywell upon loss of coolant is directed into the pressure suppression pool through the vent pipe and condenses in the pool water. As a result, the water temperature of the pressure suppression pool above the vent pipe outlet rises, and the temperature in this area becomes uniformly high due to the convection within the pool formed by heating due to steam condensation at the vent pipe outlet. On the other hand, at this point, the pool water temperature below the vent pipe outlet does not rise, and temperature stratification is formed at the height of the vent pipe outlet. At this time, consider the density state of the pressure suppression pool and the convection promoting tube between the upper and lower ends of the convection promoting tube of this means. The pressure suppression pool above the vent pipe outlet has a relatively high temperature and low density, while the convection promoting pipe side has a relatively low temperature and high density. As a result, since the water head (product of density and height: ρgh) at the lower end of the section under consideration is larger on the convection promoting tube side, a circulation is formed in which water flows down the convection promoting tube and into the pressure suppression pool. As a result, the high temperature water above the pressure suppression pool flows into the upper part of the convection promoting tube.
Since the convection promoting tube is immersed in a lower temperature outer peripheral pool, heat is dissipated through the tube wall, and the temperature gradually becomes lower as it flows down inside the convection promoting tube. Due to this action, above the vent pipe outlet, the density and hence the water head on the convection promoting pipe side are always maintained in a large state, and a driving force for circulation flowing downward through the convection promoting pipe is created. On the other hand, in the section below the outlet of the vent pipe, the convection promoting tube side first becomes high temperature due to circulation, resulting in a density (water head) state that cancels out the driving force of the circulation, but the position of the lower end of the convection promoting tube By setting the convection tube appropriately (i.e., positioning the lower end of the convection tube at a position that does not completely cancel out the downward driving force formed above), while maintaining the circulation flowing downward through the convection tube, In addition, relatively high temperature water can be allowed to flow into the region below the vent pipe outlet. Due to this action, the hot water that flows into the area below the vent pipe outlet increases the water temperature in that area, and this increases the density (water head) in the direction that cancels out the driving force of circulation formed in the area below the vent pipe outlet.
It relieves the condition and promotes circulation. By repeating the above actions, the water temperature in the area below the vent pipe outlet is also continuously increased. At this time, the water temperature in the area below the outlet of the vent pipe is approximately equal to the temperature of the water flowing in from the lower end of the convection promoting pipe, and therefore does not become lower than the water temperature of the outer peripheral pool. This allows relatively high-temperature pool water to constantly circulate in the low-temperature area below the vent pipe outlet of the pressure suppression pool, increasing the area that absorbs heat from the reactor core, and improving heat transfer to the outer pool. Not only the reactor containment vessel wall corresponding to the pressure suppression pool area where the heat area becomes high temperature, but also the convection promoting tube wall can be used as a heat transfer surface. Convection promoting tubes are generally smaller than the reactor containment vessel diameter, so they can be installed arbitrarily without affecting the reactor containment vessel pressure resistance, so the reactor containment vessel dimensions and reactor containment vessel pressure resistance can be changed. The heat transfer area can be increased without any heat transfer, and the effect of increasing the amount of heat dissipation can be obtained. As a result, even if the main dimensions of the reactor containment vessel are the same, it can be applied to a plant with higher output.
【００７４】第４の基本的実施例では、以下の動作によ
り原子炉格納容器からの放熱量を大きくしている。即ち
、原子炉格納容器外周に冷却水プールを備えた自然放熱
型原子炉格納容器において、圧力抑制室のプール水領域
だけでなくウエットウエル領域にも熱的に接するように
外周プールの水位を高くすれば、ウエットウエルを冷却
することができる。しかし、通常時に原子炉格納容器内
が常圧の場合には、原子炉格納容器の外周プールと接す
る領域に圧力抑制プールと外周プールの水位差に相当す
る圧力がかかる。そこで、原子炉格納容器の外周部に圧
力抑制室のプール水領域に熱的に接する外周プールとウ
エットウエル領域に熱的に接するウエットウエル冷却水
プールを独立に備えることにより、原子炉格納容器にか
かるプールの水頭圧を低減しつつ広い範囲を水冷による
冷却を成し、放熱を促進する。In the fourth basic embodiment, the amount of heat released from the reactor containment vessel is increased by the following operation. In other words, in a naturally heat dissipating reactor containment vessel that has a cooling water pool around the outer periphery of the reactor containment vessel, the water level of the outer circumferential pool is raised so that it is in thermal contact not only with the pool water area of the pressure suppression chamber but also with the wet well area. Then, the wet well can be cooled. However, under normal conditions, when the inside of the reactor containment vessel is at normal pressure, a pressure corresponding to the water level difference between the pressure suppression pool and the outer circumferential pool is applied to a region of the reactor containment vessel that is in contact with the outer peripheral pool. Therefore, by separately providing an outer peripheral pool in thermal contact with the pool water area of the pressure suppression chamber and a wet well cooling water pool in thermal contact with the wet well area on the outer periphery of the reactor containment vessel, While reducing the water head pressure of such a pool, a wide area can be cooled by water cooling, and heat radiation can be promoted.
【００７５】以上の基本的な実施例は、実施上互いに干
渉することがないので、それぞれを組合せて使用するこ
とができる。この場合、それぞれの効果が重畳され、そ
れぞれの手段を単独で用いた場合よりも効果を大きくす
ることができる。The basic embodiments described above do not interfere with each other in practice, so they can be used in combination. In this case, each effect is superimposed, and the effect can be made larger than when each means is used alone.
【００７６】以下に具体的な各実施例につき図面に基づ
き説明する。Each specific embodiment will be explained below based on the drawings.
【００７７】第１の基本的実施例を図１により説明する
。本実施例は、本発明を直径３４ｍの鋼製原子炉格納容
器に適用した例である。ここで原子炉格納容器直径を３
４ｍとしたのは、これだけの寸法があれば、電気出力６
００ＭＷ級から１５００ＭＷ級のプラントについては原
子炉容器，配管系および運転に必要な主要機器を、配置
上の観点からは標準的に収容できることによる。なお、
以下で述べる他の実施例も、同じ直径の格納容器を対象
としている。対象とする格納容器は、炉心１を内包する
原子炉圧力容器２、原子炉圧力容器２の外周に設置され
た圧力抑制プール５とその上部の気相空間ウエットウエ
ル６から成る圧力抑制室４、ドライウエル３と圧力抑制
プール５を連結するベント管７、鋼製の原子炉格納容器
壁８に接し前記圧力抑制プール５の外側に設置された外
周プール９から構成されている。その他の構成要素とし
ては、原子炉容器２より上部に位置し逆止弁２８を介し
て原子炉容器２と連結された蓄圧注水タンク２５と重力
落下水タンク２６、ならびに圧力抑制プール５と原子炉
容器２を逆止弁を介して連結する冠水系２７がある。本
実施例の特徴となる構成要素は、次のものである。前記
ウエットウエル６は、区画壁６３により圧力抑制プール
表面に接する第１空間６１とそうでない第２空間６２に
区画され、両空間は区画壁６３を貫通する配管６４で連
通してあるとともに、第２空間の底部と圧力抑制プール
水中をつなぐ配管６５が設けられている。また、ウエッ
トウエルの第２空間の位置にある鋼製格納容器壁８の外
側には、下部から空気を吸い込み建屋の上部から排出す
る空気流路６６が設けられている。この圧力抑制室部分
の拡大図を図２に示す。図１および図２により、本実施
例の動作を説明する。原子炉の安全設計で想定する冷却
材喪失事故時には、原子炉圧力容器２内の冷却材は高温
高圧の蒸気としてドライウエル３へ流出する。炉心１に
は制御棒（図示せず）が挿入され核***反応が停止する
が、炉心ではその後も長期に渡り崩壊熱が発生する。こ
の時、原子炉容器２の圧力低下に従い、蓄圧注水タンク
２５、重力落下水タンク２６および冠水系２７から圧力
差，重力差で冷却水が原子炉容器２に注水され、炉心１
の冠水が維持される。炉心１での崩壊熱はこの冷却水の
蒸発により除去され、破断箇所から蒸気がドライウエル
３に放出される。これにより、ドライウエル３の圧力が
上昇しベント管７内の水を押し下げ、蒸気は圧力抑制プ
ール５に流入してプール水中で凝縮される。この時ドラ
イウエル内にあった不凝縮性気体は放出された蒸気に押
し出されかつ同伴されて圧力抑制プールに流入し、プー
ル中を上昇して第一空間６１に蓄積される。この蓄積に
より、第１空間６１の圧力は上昇するため、不凝縮性気
体は配管６４を通って第２空間６２に流入する。ドライ
ウエルからウエットウエルへの不凝縮性気体の移行は、
想定した事故発生後の数分間で終了し、それ以降は原子
炉容器２から放出される蒸気のみが圧力抑制プールに流
入する。圧力抑制プール５内での蒸気凝縮の際に発生す
る潜熱によりベント管出口１３付近のプール水が加熱さ
れ、対流によりベント管出口１３から上方のプール水温
がほぼ一様に上昇する。この温度上昇につれて、プール
表面から蒸発が起こり第１空間６１内の蒸気分圧も上昇
し空間の圧力が上昇する。そして、発生した蒸気が第１
空間６１に残存している不凝縮性気体を同伴して第２空
間６２に流入する。第２空間６２に流入した蒸気は鋼製
の格納容器壁８を介して外側の流路６６を通る空気に放
熱し壁面で凝縮後、配管６５を通って圧力抑制プール５
に戻る。第２空間６２を冷却する自然通風冷却は、単位
面積当りの冷却能力は小さいが、伝熱面となる格納容器
壁８の面積が広いことおよび配管６４を通って流入する
蒸気量が少ないことから、第２空間６２に流入した蒸気
を凝縮し第１空間６１よりも低温の状態を維持すること
ができる。ここで、配管６４では第１空間６１から来る
気体の流れにより、また配管６５では配管が浸っている
圧力抑制プール水によって、一旦第２空間６２に流入し
た不凝縮性気体が第１空間６１に戻ることが防止される
。以上のように前記の動作の項で説明した動きが繰り返
されることにより、不凝縮性気体のほぼ全量が第２空間
６２に蓄積され、第１空間６１は圧力抑制プール表面温
度に等しい温度の蒸気に満たされる。ところで、想定し
た事故時における格納容器からの基本的な放熱は、高温
となった圧力抑制プール５から鋼製格納容器壁を介して
外周プール９への放熱によって達成される。本実施例に
よる放熱特性の向上を、図３により説明する。図は想定
した事故後の時間に対する格納容器圧力の変化について
、本実施例を適用した場合としない場合について比較し
ている。図中破線で示した本実施例を適用しない場合、
時間の経過につれて圧力抑制プール水温が上昇し格納容
器圧力が上昇するが、圧力抑制プール水温の上昇にとも
ない外周プールへの放熱量も増加し、ついには炉心で発
生する崩壊熱を上回り格納容器圧力は低下を始め、格納
容器圧力を容器の耐圧以下に抑えている。この成立して
いるプラント出力を規格化した出力１．０ と定義する
。図中実線のＡで示した本実施例を採用した規格化した
プラント出力１．０ の場合は、動作の項に述べたよう
に、格納容器圧力は不凝縮性気体の分圧と蒸気分圧の和
ではなく蒸気分圧のみを考慮すれば良いため、想定した
冷却材喪失事故時の最高圧力は低いものとなっている。
すなわち、本実施例では、この低くなった圧力に対応し
て圧力抑制プール水温の上昇が許容され、大気開放され
てその上限温度が１００℃に制限される外周プールとの
温度差を拡大できるため、放熱特性が向上し、同一寸法
の格納容器をより大出力のプラントに適用できる。本実
施例では圧力抑制プールの許容温度を約１２２℃から約
１４４℃に上昇させることができる。
本実施例を適用した場合、格納容器の圧力抑制は図中実
線のＢで示すように規格化したプラント出力１．６で成
立し、適用可能なプラント出力を１．６ 倍とすること
ができる。なお、格納容器圧力が低下傾向に移ると、第
２空間６２の圧力が第１空間６１の圧力より高くなり、
第２空間６２内に蓄積されていた不凝縮性気体の一部が
配管６４を通って第１空間６１に戻るが、この時点では
放熱量が崩壊熱を上回っており、放熱特性上問題とはな
らない。この不凝縮性気体の戻りを防止したい場合は、
該配管６４途中に逆止弁を設置するだけで良い。また、
本実施例では、第２空間６２での凝縮水の戻り配管６５
を設けているが、この配管を設けなくても事故時に第２
空間に水が溜るだけであり、動作上問題はない。A first basic embodiment will be explained with reference to FIG. This example is an example in which the present invention is applied to a steel reactor containment vessel with a diameter of 34 m. Here, the reactor containment vessel diameter is 3
The reason for choosing 4m is that with this size, the electrical output will be 6.
This is because for plants from 00 MW to 1,500 MW, the reactor vessel, piping system, and main equipment necessary for operation can be accommodated in a standard manner from a layout standpoint. In addition,
Other embodiments described below are also directed to containment vessels of the same diameter. The target containment vessel includes a reactor pressure vessel 2 containing a reactor core 1, a pressure suppression chamber 4 consisting of a pressure suppression pool 5 installed around the outer periphery of the reactor pressure vessel 2, and a gas phase space wet well 6 above it. It consists of a vent pipe 7 connecting the dry well 3 and the pressure suppression pool 5, and an outer peripheral pool 9 installed outside the pressure suppression pool 5 in contact with the steel reactor containment vessel wall 8. Other components include a pressure accumulation water injection tank 25 and a gravity drop water tank 26 located above the reactor vessel 2 and connected to the reactor vessel 2 via a check valve 28, as well as a pressure suppression pool 5 and a reactor There is a submersion system 27 that connects the containers 2 via check valves. The characteristic components of this embodiment are as follows. The wet well 6 is divided by a partition wall 63 into a first space 61 that is in contact with the pressure suppression pool surface and a second space 62 that is not in contact with the surface of the pressure suppression pool. A pipe 65 is provided that connects the bottom of the two spaces and the pressure suppression pool water. Further, on the outside of the steel containment vessel wall 8 located in the second space of the wet well, an air passage 66 is provided for sucking in air from the lower part and discharging it from the upper part of the building. An enlarged view of this pressure suppression chamber portion is shown in FIG. 2. The operation of this embodiment will be explained with reference to FIGS. 1 and 2. In the event of a loss of coolant accident, which is assumed in the safety design of a nuclear reactor, the coolant in the reactor pressure vessel 2 flows out into the dry well 3 as high-temperature, high-pressure steam. Control rods (not shown) are inserted into the reactor core 1 to stop the nuclear fission reaction, but decay heat continues to be generated in the reactor core for a long period of time. At this time, as the pressure in the reactor vessel 2 decreases, cooling water is injected into the reactor vessel 2 from the pressure accumulation water injection tank 25, the gravity drop water tank 26, and the flooding system 27 due to the pressure difference and gravity difference, and the reactor core 1
submergence will be maintained. Decay heat in the core 1 is removed by evaporation of this cooling water, and steam is released into the dry well 3 from the fracture site. As a result, the pressure in the dry well 3 increases, pushing down the water in the vent pipe 7, and the steam flows into the pressure suppression pool 5 and is condensed in the pool water. At this time, the non-condensable gas present in the dry well is pushed out and entrained by the released steam, flows into the pressure suppression pool, rises through the pool, and is accumulated in the first space 61. Due to this accumulation, the pressure in the first space 61 increases, so that the non-condensable gas flows into the second space 62 through the pipe 64. The migration of non-condensable gases from the dry well to the wet well is
The process ends several minutes after the assumed accident occurs, and from then on, only the steam released from the reactor vessel 2 flows into the pressure suppression pool. Pool water near the vent pipe outlet 13 is heated by latent heat generated during steam condensation in the pressure suppression pool 5, and the pool water temperature above the vent pipe outlet 13 rises almost uniformly due to convection. As this temperature rises, evaporation occurs from the pool surface, and the partial pressure of vapor within the first space 61 also rises, causing the pressure of the space to rise. Then, the generated steam
The non-condensable gas remaining in the space 61 flows into the second space 62 . The steam flowing into the second space 62 radiates heat to the air passing through the outer flow path 66 through the steel containment vessel wall 8, condenses on the wall surface, and then passes through the piping 65 to the pressure suppression pool 5.
Return to Natural draft cooling for cooling the second space 62 has a small cooling capacity per unit area, but because the area of the containment vessel wall 8, which is a heat transfer surface, is large and the amount of steam flowing in through the piping 64 is small, , the steam flowing into the second space 62 can be condensed to maintain a lower temperature than the first space 61 . Here, the non-condensable gas that once flowed into the second space 62 flows into the first space 61 by the flow of gas coming from the first space 61 in the pipe 64 and by the pressure suppression pool water in which the pipe is immersed in the pipe 65. Return is prevented. By repeating the movement described in the above operation section, almost the entire amount of non-condensable gas is accumulated in the second space 62, and the first space 61 is filled with steam having a temperature equal to the surface temperature of the pressure suppression pool. filled with. By the way, basic heat radiation from the containment vessel in the event of a hypothetical accident is achieved by heat radiation from the high-temperature pressure suppression pool 5 to the outer peripheral pool 9 via the steel containment vessel wall. The improvement in heat dissipation characteristics according to this example will be explained with reference to FIG. 3. The figure compares the change in containment vessel pressure with respect to the assumed time after the accident, with and without applying this example. When this embodiment shown by the broken line in the figure is not applied,
As time passes, the pressure suppression pool water temperature rises and the containment vessel pressure increases, but as the pressure suppression pool water temperature rises, the amount of heat released to the outer pool also increases, and eventually the pressure in the containment vessel exceeds the decay heat generated in the core. began to drop, keeping the containment vessel pressure below the vessel's withstand pressure. This established plant output is defined as a standardized output of 1.0. In the case of a normalized plant output of 1.0 using this embodiment, indicated by the solid line A in the figure, as described in the operation section, the containment vessel pressure is the partial pressure of noncondensable gas and the partial pressure of steam. Because only the steam partial pressure needs to be considered, rather than the sum of In other words, in this embodiment, the water temperature of the pressure suppression pool is allowed to rise in response to this lowered pressure, and the temperature difference between the pressure suppression pool and the outer pool, which is opened to the atmosphere and whose upper limit temperature is limited to 100°C, can be increased. , heat dissipation characteristics are improved, and containment vessels of the same size can be applied to higher output plants. In this example, the allowable temperature of the pressure suppression pool can be increased from about 122°C to about 144°C. When this example is applied, pressure suppression of the containment vessel is achieved at a normalized plant output of 1.6 as shown by the solid line B in the figure, and the applicable plant output can be increased by 1.6 times. . Note that when the containment vessel pressure shifts to a decreasing trend, the pressure in the second space 62 becomes higher than the pressure in the first space 61,
A part of the non-condensable gas accumulated in the second space 62 passes through the pipe 64 and returns to the first space 61, but at this point the amount of heat dissipated exceeds the decay heat, so there is no problem in terms of heat dissipation characteristics. It won't happen. If you want to prevent this non-condensable gas from returning,
It is sufficient to simply install a check valve in the middle of the pipe 64. Also,
In this embodiment, the condensed water return pipe 65 in the second space 62
However, even if this piping is not installed, a second pipe will be installed in the event of an accident.
There is no problem in operation, only water accumulates in the space.
【００７８】別の実施例を、図４により説明する。本実
施例で上述の実施例と異なっている点は、格納容器壁８
側で区画壁６３に段差を持たせ、第２空間６２を下側に
拡張して、その拡張した領域が圧力抑制プール５の水位
よりも上部にある外周プール水と熱的に接するようにす
るとともに、凝縮水が戻るための配管６５を、第２空間
６２で下側に拡張した領域の底部に設けたことである。
本実施例のようなプール水による冷却は、上述で述べた
空気の自然通風に比べ放熱特性が良く、第２空間６２の
冷却に必要な伝熱面積を小さくすることができるので、
大きな伝熱面積を必要とし格納容器の相対的に上部の領
域での設置，保守が必要になる空気冷却の手段を不要な
ものとすることができる。実施例全体における放熱特性
は、図３により説明したものと同じである。Another embodiment will be explained with reference to FIG. This embodiment differs from the above-mentioned embodiments in that the containment vessel wall 8
The partition wall 63 is provided with a step on the side, and the second space 62 is expanded downward so that the expanded area is in thermal contact with the peripheral pool water located above the water level of the pressure suppression pool 5. In addition, a pipe 65 for returning condensed water is provided at the bottom of the area expanded downward in the second space 62. Cooling using pool water as in this embodiment has better heat dissipation characteristics than the natural ventilation described above, and the heat transfer area required for cooling the second space 62 can be reduced.
It is possible to eliminate the need for air cooling means that require a large heat transfer area and require installation and maintenance in a relatively upper area of the containment vessel. The heat dissipation characteristics in the entire example are the same as those described with reference to FIG.
【００７９】第２の基本的実施例を図５により説明する
。図１に示した実施例との相違点は、ウエットウエル６
を区画する構造体を設ける変わりに、圧力抑制プール５
表面に１００℃以上でも飽和蒸気圧が低く、水より密度
が小さい、例えば、シリコンオイルやスピンドルオイル
のような疎水性物質の層５１を形成する点である。本実
施例では、事故時初期に蒸気とともにドライウエルから
移行する不凝縮性気体は、圧力抑制プール水５および疎
水性物質の層５１を通過してウエットウエル６に蓄積す
る。一方、ベント管７から流入する蒸気はプール水中で
凝縮し、プール水ならびに疎水性物質の層５１を加熱す
る。しかし、ウエットウエル６に接するプール表面が飽
和蒸気圧の低い疎水性物質であるため、プール水温が上
昇してもウエットウエル６内の蒸気分圧の上昇は小さく
（ほとんど０）疎水性物質の蒸気分圧を考慮する必要は
ない。そして、本実施例のように、圧力抑制プール５表
面に飽和蒸気圧が低く水より密度が小さい疎水性物質の
層５１を形成することによって、前述の動作の項で述べ
たように圧力抑制プール５表面からのプール水の蒸発が
抑制される。したがって、ウエットウエル６の圧力が低
い状態で、圧力抑制プール５の水温が高い状態を実現す
ることができる。すなわち、格納容器の寸法を変更する
ことなく圧力抑制プールの許容温度を上昇させることが
できる。また、本実施例のようにウエットウエルを空気
の自然通風で冷却する場合は、動作の項で述べたように
図１に示した実施例における区画壁６３、配管６４およ
び６５を疎水性物質で代用したと考えることもできるの
で、その放熱特性の向上は図３に示したものと同じにな
る。すなわち本実施例では、圧力抑制プールの許容温度
を約１２２℃から約１４４℃に上昇させることができ、
適用可能なプラント出力を１．６ 倍とすることができ
る。A second basic embodiment will be explained with reference to FIG. The difference from the embodiment shown in FIG.
Instead of providing a structure that partitions the pressure suppression pool 5
The point is that a layer 51 of a hydrophobic substance, such as silicone oil or spindle oil, which has a low saturated vapor pressure and a density lower than water even at 100° C. or higher is formed on the surface. In this embodiment, non-condensable gas that migrates from the dry well together with steam at the initial stage of an accident passes through the pressure suppression pool water 5 and the hydrophobic substance layer 51 and accumulates in the wet well 6. On the other hand, the steam flowing in from the vent pipe 7 condenses in the pool water and heats the pool water and the hydrophobic material layer 51. However, since the surface of the pool in contact with the wet well 6 is made of a hydrophobic substance with a low saturated vapor pressure, even if the pool water temperature rises, the increase in the partial pressure of steam inside the wet well 6 is small (almost 0), meaning that the vapor of the hydrophobic substance There is no need to consider partial pressure. As in this embodiment, by forming a layer 51 of a hydrophobic substance with a low saturated vapor pressure and a density smaller than water on the surface of the pressure suppression pool 5, the pressure suppression pool 5. Evaporation of pool water from the surface is suppressed. Therefore, it is possible to achieve a state in which the water temperature in the pressure suppression pool 5 is high while the pressure in the wet well 6 is low. That is, the allowable temperature of the pressure suppression pool can be increased without changing the dimensions of the containment vessel. In addition, when the wet well is cooled by natural ventilation as in this embodiment, the partition wall 63 and piping 64 and 65 in the embodiment shown in FIG. Since it can be considered as a substitute, the improvement in heat dissipation characteristics is the same as that shown in FIG. 3. That is, in this example, the allowable temperature of the pressure suppression pool can be increased from about 122°C to about 144°C,
The applicable plant output can be increased by 1.6 times.
【００８０】第３の基本的実施例を、図６により説明す
る。本実施例の特徴となる部分は、圧力抑制プール水中
の鋼製格納容器８に、ベント管出口１３を挾んで上下の
位置に上方開口部１０と下方開口部１１を設け、外周プ
ール９水中にあって該上方開口部１０と下方開口部１１
を連結する対流促進管１２を設けたことである。それ以
外の主要構成要素は、図１と同じである。本実施例では
、上方開口部１０とベント管出口１３との高さの差が、
ベント管出口１３と下方開口部１１との高さの差よりも
大きくなるように、ベント管出口１３と開口部１０，１
１が設置されている。A third basic embodiment will be explained with reference to FIG. The feature of this embodiment is that the steel containment vessel 8 in the pressure suppression pool is provided with an upper opening 10 and a lower opening 11 at the upper and lower positions sandwiching the vent pipe outlet 13, and the outer peripheral pool 9 is in the water. The upper opening 10 and the lower opening 11
This is because a convection promoting tube 12 is provided to connect the two. The other main components are the same as in FIG. In this embodiment, the difference in height between the upper opening 10 and the vent pipe outlet 13 is
The height difference between the vent pipe outlet 13 and the lower opening 11 is greater than the height difference between the vent pipe outlet 13 and the lower opening 11.
1 is installed.
【００８１】想定した冷却材喪失事故時に原子炉容器２
から放出される蒸気は、ベント管出口１３を通って圧力
抑制プール５に流入しプール水中で凝縮される。圧力抑
制プール５内での蒸気凝縮の際に発生する潜熱により蒸
気出口１３付近のプール水が加熱され、対流によりベン
ト管出口１３から上方のプール水温がほぼ一様に上昇す
る。これにより、対流促進管１２の設置された区間の密
度状態は、高温となった圧力抑制プール水で小さく低温
の対流促進管１２内で大きくなる。この密度差により、
対流促進管１２を下降する流れが生じ、上方開口部１０
を通って高温の圧力抑制プール水が対流促進管１２の上
部に流入する。流入した高温水は対流促進管１２が外周
プール水に浸かっていることから管内で冷却され、徐々
に低温となりながら流下する。この結果、対流促進管１
２の設置されている区間の密度の大小状態は変わらず、
対流促進管１２を下降する流れが定常的に形成される。
そして、外周プール水温より高い状態の水が下方開口部
１１を通って、圧力抑制プール５のベント管出口１３よ
り下方の領域に流入し該領域を温めるのは、前述の動作
の項に記載した通りである。想定した冷却材喪失事故後
の、ある時刻における圧力抑制プール５と対流促進管１
２の高さ方向の温度分布ならびに密度分布を図７に示す
。温度的には、圧力抑制プール５のベント管出口１３よ
り上方の区間がベント管からの蒸気により一様に高温と
なり、対流促進管１２内で冷却されるため高さが低くな
るにつれて直線的に水温が低下し、この下端における温
度の水が流入する結果、圧力抑制プール５のベント管出
口１３より下方の領域もほぼその温度となる。ここで、
対流促進管１２内で温度が直線的に低下するのは、対流
促進管の直径が一様であり、結果外周プールでの冷却も
高さ方向に一様であるためである。また、圧力抑制プー
ル５のベント管出口１３より下方の領域の水温が流入し
た水温とほぼ同じ温度としているのは、事象が長期間に
わたる緩やかなものであり準定常と扱えるためである。
水の密度は水温に逆比例することは知られており、図７
の右側に示したように温度分布を裏返したような分布と
なる。図から分かるように、ベント管出口１３より上方
の区間では、対流促進管１２側の密度が大きく対流促進
管内を下降する方向に駆動力（水頭）が働く。この下向
きの駆動力の総和は、図中で両領域の密度の線により形
成される三角形ａの面積となる。一方、ベント管出口１
３より下側の区間では、逆に圧力抑制プール側の密度が
大きく、この区間での駆動力は上方で発生した下向きの
駆動力を打ち消す方向となる。このベント管出口より下
方で発生する上向きの駆動力の総和（すなわち、図中の
密度の線で形成される三角形ｂの面積）が、上方で発生
する下向きの駆動力の総和より小さければ、全体的な流
れとして対流促進管１２内を下降する流れとなる。
すなわち、図中の上の三角形ａの面積が下の三角形ｂの
面積より大きい条件であれば、対流促進管１２内を下降
する全体的な流れが定常的に形成され本手段が有効に動
作する。このことから本実施例のように対流促進管１２
の形状が一様で冷却状況も一様となる場合に、本手段が
有効に動作する条件は、前記の本実施例の説明にあるよ
うに、上方開口部１０とベント管出口１３との高さの差
（図中のＬ１）をベント管出口１３と下方開口部１１と
の高さの差（図中のＬ２）よりも大きくすることである
。[0081] At the time of the hypothetical loss of coolant accident, reactor vessel 2
The steam released from the pressure suppression pool 5 flows through the vent pipe outlet 13 and is condensed in the pool water. Pool water near the steam outlet 13 is heated by latent heat generated during steam condensation in the pressure suppression pool 5, and the pool water temperature above the vent pipe outlet 13 increases almost uniformly due to convection. As a result, the density state of the section where the convection promoting pipe 12 is installed is small in the high temperature pressure suppression pool water and becomes large in the low temperature convection promoting pipe 12. Due to this density difference,
A flow descends through the convection promoting tube 12 and the upper opening 10
Through the high temperature pressure suppression pool water flows into the upper part of the convection promoting tube 12. Since the convection promoting tube 12 is immersed in the outer peripheral pool water, the inflowing high temperature water is cooled within the tube, and gradually becomes lower in temperature as it flows down. As a result, convection promoting tube 1
The density of the section where 2 is installed remains unchanged,
A flow descending through the convection promoting tube 12 is constantly formed. The water whose temperature is higher than that of the outer pool passes through the lower opening 11 and flows into the area below the vent pipe outlet 13 of the pressure suppression pool 5 to warm the area, as described in the operation section above. That's right. Pressure suppression pool 5 and convection promoting pipe 1 at a certain time after a hypothetical loss of coolant accident
FIG. 7 shows the temperature distribution and density distribution in the height direction of No. 2. In terms of temperature, the section above the vent pipe outlet 13 of the pressure suppression pool 5 becomes high temperature uniformly due to the steam from the vent pipe, and as it is cooled within the convection promotion pipe 12, the temperature increases linearly as the height decreases. As a result of the water temperature decreasing and water having the temperature at this lower end flowing in, the area below the vent pipe outlet 13 of the pressure suppression pool 5 also has approximately the same temperature. here,
The reason why the temperature decreases linearly within the convection promoting tube 12 is that the diameter of the convection promoting tube is uniform, and as a result, the cooling in the outer circumferential pool is also uniform in the height direction. Furthermore, the reason why the water temperature in the area below the vent pipe outlet 13 of the pressure suppression pool 5 is set to be approximately the same temperature as the inflow water temperature is because the event is gradual over a long period of time and can be treated as quasi-steady. It is known that the density of water is inversely proportional to the water temperature, and Figure 7
As shown on the right side of , the temperature distribution becomes an inverted version of the temperature distribution. As can be seen from the figure, in the section above the vent pipe outlet 13, the density on the convection promoting pipe 12 side is large, and a driving force (hydraulic head) acts in a downward direction inside the convection promoting pipe. The sum total of this downward driving force is the area of triangle a formed by the density lines of both regions in the figure. On the other hand, vent pipe outlet 1
In the section below 3, on the contrary, the density on the pressure suppression pool side is large, and the driving force in this section cancels out the downward driving force generated above. If the sum of the upward driving forces generated below the vent pipe outlet (that is, the area of triangle b formed by the density line in the figure) is smaller than the sum of the downward driving forces generated above, then the total The flow becomes a downward flow within the convection promoting tube 12 as a flow. That is, under the condition that the area of the upper triangle a in the figure is larger than the area of the lower triangle b, the overall flow descending within the convection promoting tube 12 is formed steadily and the present means operates effectively. . For this reason, as in this embodiment, the convection promoting tube 12
When the shape of the vent pipe is uniform and the cooling condition is also uniform, the conditions for this means to operate effectively are as follows: The purpose is to make the difference in height (L1 in the figure) larger than the difference in height between the vent pipe outlet 13 and the lower opening 11 (L2 in the figure).
【００８２】以上のごとく、本実施例では動作の項に述
べたと同じ動作を実現でき、圧力抑制プール５から外周
プール９への放熱面積を拡大して放熱特性を向上できる
。本実施例の放熱特性の向上を、図８により説明する。
図は、前述の図３と同様に想定した事故後の時間に対す
る格納容器圧力の変化について、本実施例を適用した場
合としない場合について比較している。なお、図中実線
で示した本実施例を適用した場合の条件としては、直径
５０ｍｍの対流促進管１２を約５００本設置したことを
想定している。対流促進管は１２は、格納容器の全周に
わたって設置することができるので、実施上の問題はな
い。規格化したプラント出力１．０ に本実施例を適用
した場合は、図中の実線Ａで示すように放熱面積が拡が
っていることから、想定した事故時の最高圧力が実施例
を適用しない場合（図中の破線）より低くなっている。
この低くなった圧力に対応した分だけ、より大出力のプ
ラントに適用できるわけである。適用可能な規格化した
プラント出力は、図中の実線Ｂに示すように１．５であ
り、本実施例により適用可能なプラント出力を１．５倍
にすることができる。As described above, in this embodiment, the same operation as described in the operation section can be realized, and the heat radiation area from the pressure suppression pool 5 to the outer peripheral pool 9 can be expanded to improve the heat radiation characteristics. The improvement in heat dissipation characteristics of this example will be explained with reference to FIG. 8. The figure compares the case where this embodiment is applied and the case where the present embodiment is not applied regarding the change in the containment vessel pressure with respect to time after the accident, which is assumed similarly to FIG. 3 described above. Note that, as a condition for applying this embodiment shown by a solid line in the figure, it is assumed that approximately 500 convection promoting tubes 12 having a diameter of 50 mm are installed. Since the convection promoting pipes 12 can be installed all around the containment vessel, there is no problem in implementation. When this example is applied to a standardized plant output of 1.0, the heat dissipation area expands as shown by the solid line A in the figure, so the maximum pressure at the time of the assumed accident is lower than when this example is not applied. (dashed line in the figure). It can be applied to plants with higher output to accommodate this lower pressure. The applicable normalized plant output is 1.5, as shown by the solid line B in the figure, and this embodiment can increase the applicable plant output by 1.5 times.
【００８３】別の実施例を図９により説明する。図６に
示した実施例との相違点は、上方開口部１０及び下方開
口部１１の原子炉格納容器壁８の内外に隔離弁２１を備
えた点である。なお、図９は図６のうち圧力抑制プール
及び外周プール部分を切り出して示したものである。通
常運転時には隔離弁２１は開状態であるが、定期検査時
に隔離弁２１を閉じることにより、原子炉格納容器と対
流促進管１２を隔離して、対流促進管１２の交換などの
保守点検を容易にすることができる。また、何らかの理
由で対流促進管１２からのリークが発生した場合を想定
しても、該隔離弁２１の閉操作により原子炉格納容器の
隔離を確実なものとすることができる。さらに別の実施
例を図１０及び図１１により説明する。これまでの実施
例との相違点は、上方開口部１０に連結する上方ヘッダ
管３１、下方開口部１１に連結する下方ヘッダ管３２、
及び上方ヘッダ管３１と下方ヘッダ管３２を連結する伝
熱管３３によって対流促進管を構成していることである
。図１０は圧力抑制プール及び外周プール部分の縦断面
図であり、図１１はＡ−Ａ′から見た横断面図である。
上方ヘッダ管３１と下方ヘッダ管３２内の水温は、流入
する水によってそれぞれ一様となるので、動作的には上
述の実施例と同じである。本実施例によって、上部開口
部１０および下部開口部１１の数を少なくすることがで
き、加工性，製造性を向上することができるとともに、
原子炉格納容器の直径にかかわらずヘッダ管の直径を調
整することで伝熱管３３を必要なだけ設置することがで
きる。また、伝熱管３３を曲がりを持った形状とするこ
とによって、伝熱管３３の温度変化による伸縮を吸収す
ることができる。Another embodiment will be explained with reference to FIG. The difference from the embodiment shown in FIG. 6 is that isolation valves 21 are provided inside and outside the reactor containment vessel wall 8 of the upper opening 10 and the lower opening 11. In addition, FIG. 9 shows the pressure suppression pool and the outer peripheral pool cut out from FIG. 6. The isolation valve 21 is open during normal operation, but by closing the isolation valve 21 during regular inspections, the reactor containment vessel and the convection promoting tube 12 are isolated, making maintenance inspections such as replacing the convection promoting tube 12 easier. It can be done. Further, even if it is assumed that a leak occurs from the convection promoting pipe 12 for some reason, isolation of the reactor containment vessel can be ensured by closing the isolation valve 21. Yet another embodiment will be described with reference to FIGS. 10 and 11. The differences from the previous embodiments include an upper header pipe 31 connected to the upper opening 10, a lower header pipe 32 connected to the lower opening 11,
The heat transfer tube 33 connecting the upper header tube 31 and the lower header tube 32 constitutes a convection promoting tube. FIG. 10 is a longitudinal cross-sectional view of the pressure suppression pool and the outer peripheral pool portion, and FIG. 11 is a cross-sectional view taken along line A-A'. Since the water temperatures in the upper header pipe 31 and the lower header pipe 32 are made uniform by the inflowing water, the operation is the same as in the above-described embodiment. According to this embodiment, it is possible to reduce the number of upper openings 10 and lower openings 11, improve workability and manufacturability, and
Regardless of the diameter of the reactor containment vessel, the required number of heat transfer tubes 33 can be installed by adjusting the diameter of the header tube. Moreover, by forming the heat exchanger tube 33 into a curved shape, expansion and contraction of the heat exchanger tube 33 due to temperature changes can be absorbed.
【００８４】別の実施例を図１２により説明する。本実
施例では、対流促進管を上部の方では上方開口部１０に
接続する上方ヘッダ管３１と下方ヘッダ管３２および両
ヘッダ管を連結する複数の伝熱管３３で構成し、下部の
方では該下方ヘッダ管３２と下方開口部１１を相対的に
大口径の配管３４により前記伝熱管３３よりも少ない本
数で連結したことを特徴としている。本実施例における
、上方開口部１０と下方開口部１１の区間における圧力
抑制プールと対流促進管の高さ方向の温度分布ならびに
密度分布を、図１３に示す。本実施例の場合、対流促進
管側では、上部と下部で外周プールに接する表面積が一
様でないため、冷却も表面積の大きい上部の区間で大き
くなる。この結果、対流促進管内での温度分布は、上部
の区間で温度低下率が大きく下部では小さくなり、密度
分布もそれに対応して図に示したようになる。この場合
、下部の区間での対流促進管を下降する流れを打ち消す
ような駆動力の発生も小さくなり、下方開口部１１を設
置する位置を図７に示した実施例の場合に比べてより下
側の位置に設置することができる。これによって、圧力
抑制プール５のベント管出口１３より下側において、有
効に活用できる領域を拡大することができる。Another embodiment will be explained with reference to FIG. In this embodiment, the convection promoting tube is composed of an upper header tube 31 and a lower header tube 32 connected to the upper opening 10 and a plurality of heat exchanger tubes 33 connecting both header tubes in the upper part, and It is characterized in that the lower header pipe 32 and the lower opening 11 are connected by a relatively large-diameter pipe 34 with a smaller number than the heat transfer pipes 33. FIG. 13 shows the temperature distribution and density distribution in the height direction of the pressure suppression pool and the convection promoting tube in the section between the upper opening 10 and the lower opening 11 in this example. In the case of this embodiment, on the convection promoting tube side, since the surface area in contact with the outer circumferential pool is not uniform at the upper and lower parts, cooling is also large in the upper section where the surface area is large. As a result, the temperature distribution within the convection promoting tube has a temperature decrease rate that is large in the upper section and small in the lower section, and the density distribution is correspondingly as shown in the figure. In this case, the generation of driving force that cancels out the flow descending through the convection promoting tube in the lower section is also reduced, and the lower opening 11 is installed at a lower position than in the embodiment shown in FIG. It can be installed in a side position. Thereby, the area below the vent pipe outlet 13 of the pressure suppression pool 5 that can be effectively utilized can be expanded.
【００８５】第４の基本的実施例を図１４により説明す
る。図１４は圧力抑制室と外周プール部分を示したもの
である。圧力抑制プール５とウエットウエル６から成る
圧力抑制室４の外周に原子炉格納容器壁８に接して、主
に圧力抑制プール５と熱的に接する外周プール９と、ウ
エットウエル６に熱的に接するウエットウエル冷却水プ
ール４１がある。また、ウエットウエル６の原子炉格納
容器壁８に円周方向にリング状構造物４２を設けている
。原子炉格納容器外の冷却用プールの水位の総和（実施
例では外周プール９の水位とウエットウエル冷却水プー
ル４１の水位の和）を圧力抑制プール水位よりも高くす
ると、吸熱源であるプール水に対する伝熱面積が確保さ
れウエットウエル６からの放熱の増加によって放熱特性
が向上する。本実施例のように、原子炉格納容器外にあ
る冷却用の水のうち圧力抑制プール５の水位より過度に
高くなる部分については下側の外周プール９とは独立し
たプールとすることにより、圧力抑制プール５部分で通
常運転時に水位差に基づく過度の外圧（水頭圧）がかか
ることを防止できる。また、別置きにしたウエットウエ
ル冷却水プール４１の水位により原子炉格納容器壁にか
かる外圧については、ウエットウエル６内の該当部分の
原子炉格納容器壁８にリング状構造物４２を設けること
により、原子炉格納容器壁の板厚を変更することなく対
処することができる。このリング状構造物は、気相空間
であるウエットウエル６の領域に設置するだけで良く、
水中に設置して水の対流を阻害する場合とは異なり、壁
面での凝縮伝熱を阻害することはなく放熱特性を劣化さ
せることはない。かえって、壁面での凝縮液膜の発達を
構造物で防止し、液膜の厚さの増加による壁面での伝熱
特性を向上させることも期待できる。A fourth basic embodiment will be explained with reference to FIG. FIG. 14 shows the pressure suppression chamber and the peripheral pool portion. On the outer periphery of the pressure suppression chamber 4 consisting of a pressure suppression pool 5 and a wet well 6, there is an outer circumferential pool 9 which is in contact with the reactor containment vessel wall 8 and is mainly in thermal contact with the pressure suppression pool 5, and which is thermally connected to the wet well 6. There is an adjacent wet well cooling water pool 41. Further, a ring-shaped structure 42 is provided on the reactor containment vessel wall 8 of the wet well 6 in the circumferential direction. When the total water level of the cooling pool outside the reactor containment vessel (in the embodiment, the sum of the water level of the outer peripheral pool 9 and the water level of the wet well cooling water pool 41) is made higher than the pressure suppression pool water level, the pool water, which is a heat absorption source, The heat transfer area for the wet well 6 is secured, and the heat radiation characteristics are improved by increasing the heat radiation from the wet well 6. As in this embodiment, the part of the cooling water outside the reactor containment vessel whose water level is excessively higher than the water level of the pressure suppression pool 5 is made into a pool independent of the lower peripheral pool 9. It is possible to prevent excessive external pressure (head pressure) from being applied to the pressure suppression pool 5 portion during normal operation based on the water level difference. In addition, external pressure applied to the reactor containment vessel wall due to the water level of the wet well cooling water pool 41 placed separately can be reduced by providing a ring-shaped structure 42 on the reactor containment vessel wall 8 in the corresponding portion of the wet well 6. This can be done without changing the thickness of the reactor containment vessel wall. This ring-shaped structure only needs to be installed in the region of the wet well 6, which is a gas phase space.
Unlike when installed underwater, which inhibits water convection, it does not inhibit condensed heat transfer on the wall surface and does not deteriorate heat dissipation characteristics. On the contrary, it can be expected that the structure will prevent the development of a condensed liquid film on the wall surface and improve the heat transfer characteristics on the wall surface by increasing the thickness of the liquid film.
【００８６】以上に述べた各基本的実施例のうち、第１
と第４の各基本的実施例を組合せた一実施例を図１５に
より説明する。本実施例は基本的に、図１に説明した実
施例と図１４に説明した実施例を組合せたものである。
本実施例では、区画したウエットウエルのうち第２空間
６２に対応する部分に、ウエットウエル冷却水プール４
１とリング状構造物４２を設置している。これにより第
２空間の冷却を空気の自然通風冷却よりも放熱特性の良
いプール水による冷却とし、必要な伝熱面積を低減する
ことによって原子炉格納容器の外部で相対的に上方にお
ける冷却手段の設置を不要なものとしている。これによ
り、建設性，保守性の向上が可能となっている。また、
図５に示した実施例と図１４に示した実施例を組合せる
ことも同様に可能であることは、説明するまでもないと
考える。Among the basic embodiments described above, the first
An embodiment in which the above and fourth basic embodiments are combined will be described with reference to FIG. 15. This embodiment is basically a combination of the embodiment described in FIG. 1 and the embodiment described in FIG. In this embodiment, a wet well cooling water pool 4 is provided in a portion of the divided wet well that corresponds to the second space 62.
1 and a ring-shaped structure 42 are installed. As a result, the second space is cooled by pool water, which has better heat dissipation characteristics than natural draft cooling of air, and by reducing the required heat transfer area, cooling means outside the reactor containment vessel and relatively above can be cooled. This makes installation unnecessary. This makes it possible to improve constructability and maintainability. Also,
It goes without saying that it is also possible to combine the embodiment shown in FIG. 5 and the embodiment shown in FIG. 14.
【００８７】第３と第４の各基本的実施例を組合せた一
実施例を図１６により説明する。本実施例は、原子炉格
納容器壁８の外側において圧力抑制プール５部分に図６
の実施例に示した対流促進管１２を、ウエットウエル６
部分に図１４の実施例に示したウエットウエル冷却水プ
ール４１とリング状構造物４２を設置している。これに
より、圧力抑制プール５からの放熱面積を拡大するとと
もに、ウエットウエルからの放熱特性を向上しかつ原子
炉格納容器壁８の外圧に対する耐圧性を向上させている
。An embodiment that combines the third and fourth basic embodiments will be described with reference to FIG. 16. In this embodiment, the pressure suppression pool 5 portion is placed outside the reactor containment vessel wall 8 as shown in FIG.
The convection promoting tube 12 shown in the embodiment is placed in the wet well 6.
A wet well cooling water pool 41 and a ring-shaped structure 42 shown in the embodiment of FIG. 14 are installed in this part. This expands the heat radiation area from the pressure suppression pool 5, improves the heat radiation characteristics from the wet well, and improves the pressure resistance of the reactor containment vessel wall 8 against external pressure.
【００８８】第１と第３と第４の各基本的実施例を組合
せた一実施例を、図１７により説明する。本実施例は基
本的に、図１，図６および図１４に説明した実施例を組
合せたものである。本実施例では、ウエットウエルを区
画することで圧力抑制プールの許容温度を上昇させ、圧
力抑制プール５に対応した領域に対流促進管１２を設置
して放熱面積を拡大するとともに、ウエットウエルの第
２空間６２の冷却のために外周プール９とは別置きにし
たウエットウエル冷却水プール４１とリング状構造物４
２を設置して、容器の通常運転時の耐圧性，建設性なら
びに保守性を向上している。放熱特性の向上については
、圧力抑制プールの許容温度の上昇と伝熱面積の拡大の
効果が重なりあって、図１８に示すように適用可能なプ
ラント出力を２．３倍（成立する規格化したプラント出
力が２．３）とすることができる。ところで、圧力抑制
プール内の高温領域拡大は、従来技術の項に述べた日本
原子力学会「１９８９年秋の大会」の発表から、圧力抑
制プール中に対流促進板を設置することで実現すること
が知られている。この技術と第１の基本的実施例を組合
せた一実施例を図１９により説明する。本実施例は、図
１に示した実施例において、圧力抑制プール５中に原子
炉格納容器壁８に沿って対流促進板７０を設置したもの
である。このとき対流促進板７０の形状を、その上端と
下端がベント管出口１３を挾む高さ関係にあり、上端と
ベント管出口１３の高さの差がベント管出口と下端の高
さの差より大きくすることで、圧力抑制プール内の高温
領域が拡大することは、前記の発表で述べられたとおり
である。本実施例によれば、対流促進板７０の働きによ
り圧力抑制プール内の高温領域が拡大し、原子炉格納容
器壁８の部分に限定されるけれども放熱面積が拡大する
とともに、ウエットウエル６内の不凝縮性気体を第２空
間６２に集中的に集められるので、圧力抑制プールの許
容水温を上昇させることができる。これにより、放熱面
積の拡大とプール間の温度差の増大で放熱特性を拡大す
ることができる。An embodiment in which the first, third, and fourth basic embodiments are combined will be described with reference to FIG. 17. This embodiment is basically a combination of the embodiments described in FIGS. 1, 6, and 14. In this embodiment, the permissible temperature of the pressure suppression pool is increased by dividing the wet well, and the convection promoting tube 12 is installed in the area corresponding to the pressure suppression pool 5 to expand the heat dissipation area. A wet well cooling water pool 41 and a ring-shaped structure 4 are provided separately from the outer peripheral pool 9 to cool the two spaces 62.
2 has been installed to improve the pressure resistance of the container during normal operation, ease of construction, and ease of maintenance. Regarding the improvement of heat dissipation characteristics, the effect of increasing the allowable temperature of the pressure suppression pool and expanding the heat transfer area overlaps, and as shown in Figure 18, the applicable plant output is increased by 2.3 times (normalized The plant output can be 2.3). By the way, it is known from the presentation at the ``1989 Autumn Conference'' of the Atomic Energy Society of Japan that the expansion of the high temperature region in the pressure suppression pool can be achieved by installing a convection promoting plate in the pressure suppression pool. It is being An example in which this technique is combined with the first basic example will be described with reference to FIG. 19. In this embodiment, a convection promoting plate 70 is installed along the reactor containment vessel wall 8 in the pressure suppression pool 5 in the embodiment shown in FIG. At this time, the shape of the convection promoting plate 70 is such that its upper end and lower end are in a height relationship sandwiching the vent pipe outlet 13, and the difference in height between the upper end and the vent pipe outlet 13 is the difference in height between the vent pipe outlet and the lower end. As stated in the above presentation, making the pressure suppression pool larger expands the high temperature region within the pressure suppression pool. According to this embodiment, the high temperature area in the pressure suppression pool is expanded by the action of the convection promoting plate 70, and the heat dissipation area is expanded although it is limited to the reactor containment vessel wall 8, and the heat radiation area in the wet well 6 is expanded. Since the non-condensable gas can be concentrated in the second space 62, the allowable water temperature of the pressure suppression pool can be increased. Thereby, the heat dissipation characteristics can be expanded by increasing the heat dissipation area and increasing the temperature difference between the pools.
【００８９】なお、原子炉格納容器壁が主としてコンク
リートで製造されたプラントにおいても、図２０の一実
施例に示すように、圧力抑制プールおよびウエットウエ
ルに対応した領域を伝熱特性の良い鋼製とすれば、上述
の各基本的実施例を適用することができる。この実施例
においては、建屋の主要な構造壁は外周プール９の外側
の壁であり、従来コンクリートであった原子炉格納容器
壁を鋼性の原子炉格納容器壁８としても、建屋強度上問
題となることはない。本実施例では、鋼性の原子炉格納
容器壁８をその一部に持つ圧力抑制室内のウエットウエ
ルを区画して第１空間６１と第２空間６２を設置すると
ともに、鋼製の原子炉格納容器壁８部分にある圧力抑制
プール部分に対流促進管１２を設置している。これによ
り、圧力抑制プールの許容水温を上昇させるとともに外
周プール９への放熱面積を拡大している。[0089] Even in plants where the reactor containment vessel walls are mainly made of concrete, the areas corresponding to the pressure suppression pool and wet well are made of steel with good heat transfer properties, as shown in an example in Fig. 20. If so, each of the basic embodiments described above can be applied. In this embodiment, the main structural wall of the building is the outer wall of the peripheral pool 9, and even if the reactor containment vessel wall 8, which was conventionally made of concrete, is made of steel, there will be problems in terms of the strength of the building. It will never be. In this embodiment, a wet well in a pressure suppression chamber having a steel reactor containment vessel wall 8 as a part is divided into a first space 61 and a second space 62, and a steel reactor containment vessel wall 8 is used as a first space 61 and a second space 62. A convection promoting pipe 12 is installed in a pressure suppressing pool part in a part of the container wall 8. This increases the permissible water temperature of the pressure suppression pool and expands the heat radiation area to the outer peripheral pool 9.
【００９０】以上に各手段の代表的な組合せを示したが
、他の組合せにおいても実施上あるいは効果上で、互い
に干渉しあい問題となることはない。Although typical combinations of each means have been shown above, other combinations do not interfere with each other and cause problems in terms of implementation or effectiveness.
【００９１】[0091]
【発明の効果】請求項１の発明によれば、原子炉格納容
器の圧力抑制プール水の許容温度を格納容器の耐圧相当
の飽和蒸気温度にまで高めることが出来、その分だけ圧
力抑制プールとその外側との間の温度差を大きく出来、
放熱能力が高まるから、原子炉格納容器の圧力抑制効果
が向上し、より大出力な原子力プラントに対する原子炉
格納容器の圧力抑制手段として利用できるという効果が
得られる。According to the invention of claim 1, the permissible temperature of the pressure suppression pool water in the reactor containment vessel can be increased to the saturated steam temperature equivalent to the pressure resistance of the containment vessel, and the pressure suppression pool water can be increased by that much. The temperature difference between it and the outside can be increased,
Since the heat dissipation capacity is increased, the pressure suppression effect of the reactor containment vessel is improved, and the effect can be obtained that it can be used as a means for suppressing the pressure of the reactor containment vessel in a higher output nuclear power plant.
【００９２】請求項２の発明によれば、請求項１による
効果を圧力抑制室内でコンパクトな構成で達成できると
いう効果が得られる。According to the invention of claim 2, the effect of claim 1 can be achieved with a compact structure within the pressure suppression chamber.
【００９３】請求項３の発明によれば、請求項１又は請
求項２による発明の効果に加えて、圧力抑制室のプール
水領域から外周プール水への熱伝導効率が良くしてより
一層放熱効果を高め、原子炉格納容器の圧力抑制効果を
より一層向上するという効果が得られる。According to the invention of claim 3, in addition to the effects of the invention according to claim 1 or claim 2, the efficiency of heat conduction from the pool water area of the pressure suppression chamber to the peripheral pool water is improved, resulting in further heat dissipation. The effect of increasing the effect and further improving the pressure suppression effect of the reactor containment vessel can be obtained.
【００９４】請求項４の発明によれば、プール水の循環
動作と、その循環路による放熱面積の拡大により放熱能
力が高まるから、原子炉格納容器の圧力抑制効果が向上
し、より大出力な原子力プラントに対する原子炉格納容
器の圧力抑制手段として利用できるという効果が得られ
る。According to the invention of claim 4, the heat dissipation capacity is increased by the circulation operation of the pool water and the expansion of the heat dissipation area by the circulation path, so the pressure suppression effect of the reactor containment vessel is improved, and a higher output is achieved. The effect can be obtained that it can be used as a pressure suppression means for a reactor containment vessel in a nuclear power plant.
【００９５】請求項５によれば、請求項４の発明による
効果に加えて、循環流路の途中を冷却手段によりよく冷
却できるので温度差を大きくして放熱作用がよりよく成
され、原子炉格納容器の圧力抑制効果がより一層向上す
る。According to claim 5, in addition to the effect of the invention of claim 4, since the middle of the circulation flow path can be well cooled by the cooling means, the temperature difference is increased and the heat dissipation effect is better achieved. The pressure suppression effect of the containment vessel is further improved.
【００９６】請求項６の発明によれば、請求項４の発明
と同等の効果が得られる。According to the invention of claim 6, the same effect as the invention of claim 4 can be obtained.
【００９７】請求項７の発明によれば、請求項５の発明
と同等の効果が得られる。According to the invention of claim 7, the same effect as the invention of claim 5 can be obtained.
【００９８】請求項８の発明によれば、請求項１の発明
と同等の効果が得られる。According to the invention of claim 8, the same effect as the invention of claim 1 can be obtained.
【００９９】請求項９の発明によれば、請求項８の発明
の効果に加えて、圧力抑制室のプール水領域から外周プ
ール水への熱伝導効率が良くしてより一層放熱効果を高
め、原子炉格納容器の圧力抑制効果をより一層向上する
という効果が得られる。According to the invention of claim 9, in addition to the effect of the invention of claim 8, the heat conduction efficiency from the pool water region of the pressure suppression chamber to the peripheral pool water is improved to further enhance the heat dissipation effect. The effect of further improving the pressure suppression effect of the reactor containment vessel can be obtained.
【０１００】請求項１０の発明によれば、ウエットウエ
ルの蒸気分圧の飽和温度から始まるプール水の蒸発を、
ウエットウエルの全圧力の飽和温度から始まる様に変更
出来て、同じウエットウエル圧力下においても、圧力抑
制プール水温度をより高い温度で存在させることが出来
るため、圧力抑制プールと原子炉格納容器外との温度差
を大きくして放熱効果を向上し、原子炉格納容器の圧力
抑制効果が向上し、より大出力な原子力プラントに対す
る原子炉格納容器の圧力抑制手段として利用できるとい
う効果が得られる。According to the tenth aspect of the invention, the evaporation of pool water starts from the saturation temperature of the steam partial pressure in the wet well.
It can be changed to start from the saturation temperature of the total pressure of the wet well, and even under the same wet well pressure, the pressure suppression pool water temperature can exist at a higher temperature, so the pressure suppression pool and outside of the reactor containment vessel can be The heat dissipation effect is improved by increasing the temperature difference between the reactor containment vessel and the pressure suppressing effect of the reactor containment vessel, which can be used as pressure suppressing means for the reactor containment vessel for higher output nuclear power plants.
【０１０１】請求項１１の発明によれば、圧力抑制プー
ルが伝熱性の良い鋼製の壁を介して冷却手段に冷却され
るから請求項１０の発明による効果をよりきわだたせる
ことが出来る。According to the invention of claim 11, the pressure suppression pool is cooled by the cooling means through the steel wall having good heat conductivity, so that the effect of the invention of claim 10 can be more pronounced.
【０１０２】請求項１２の発明によれば、原子炉格納容
器の圧力抑制プール水の許容温度を格納容器の耐圧相当
の飽和蒸気温度にまで高めることが出来、その分だけ圧
力抑制プールと外周プールとの間の温度差を大きく出来
、放熱能力が高まる上、圧力抑制プールは外周プールに
よる水冷を受けるから、原子炉格納容器の圧力抑制効果
が向上し、より大出力な原子力プラントに対する原子炉
格納容器の圧力抑制手段として利用できるという効果が
得られる。According to the invention of claim 12, the permissible temperature of the pressure suppression pool water in the reactor containment vessel can be increased to the saturated steam temperature equivalent to the pressure resistance of the containment vessel, and the pressure suppression pool and the peripheral pool can be increased by that amount. In addition, the pressure suppression pool receives water cooling from the outer pool, which improves the pressure suppression effect of the reactor containment vessel. This has the advantage that it can be used as a means for suppressing pressure in a container.
【０１０３】請求項１３の発明によれば、請求項１２の
発明による効果に加えて、圧力抑制プール水水面に接し
ない領域から圧力抑制プール水中へ凝縮した流体を戻し
て圧力抑制プール水に供することが出来る。According to the invention of claim 13, in addition to the effect of the invention of claim 12, the fluid condensed into the pressure suppression pool water is returned from the area not in contact with the pressure suppression pool water surface to serve as the pressure suppression pool water. I can do it.
【０１０４】請求項１４の発明によれば、ウエットウエ
ルの蒸気分圧の飽和温度から始まるプール水の蒸発を、
ウエットウエルの全圧力の飽和温度から始まる様に変更
出来て、同じウエットウエル圧力下においても、圧力抑
制プール水温度をより高い温度で存在させることが出来
るため、圧力抑制プールと原子炉格納容器外との温度差
を大きくして放熱能力が高まる上、圧力抑制プールは外
周プールによる水冷を受けるから、原子炉格納容器の圧
力抑制効果が向上し、より大出力な原子力プラントに対
する原子炉格納容器の圧力抑制手段として利用できると
いう効果が得られる。According to the fourteenth aspect of the invention, the evaporation of pool water starts from the saturation temperature of the steam partial pressure in the wet well.
It can be changed to start from the saturation temperature of the total pressure of the wet well, and even under the same wet well pressure, the pressure suppression pool water temperature can exist at a higher temperature, so the pressure suppression pool and outside of the reactor containment vessel can be In addition, the pressure suppression pool is water-cooled by the outer peripheral pool, which improves the pressure suppression effect of the reactor containment vessel, making it easier to use the reactor containment vessel for higher output nuclear power plants. This has the advantage that it can be used as a pressure suppressing means.
【０１０５】請求項１５の発明によれば、対流促進管を
通してのプール水の循環動作と、その対流促進管による
放熱面積の拡大と、対流促進管を外周プールで冷却する
ことにより、放熱能力が高まるから、原子炉格納容器の
圧力抑制効果が向上し、より大出力な原子力プラントに
対する原子炉格納容器の圧力抑制手段として利用できる
という効果が得られる。According to the fifteenth aspect of the invention, the heat dissipation capacity is increased by circulating the pool water through the convection promoting tube, expanding the heat dissipation area by the convection promoting tube, and cooling the convection promoting tube in the outer peripheral pool. As a result, the pressure suppression effect of the reactor containment vessel is improved, and the effect can be obtained that it can be used as a means for suppressing the pressure of the reactor containment vessel for a higher output nuclear power plant.
【０１０６】請求項１６の発明によれば、圧力抑制プー
ル水の循環が維持できる密度差が長期に確実に維持でき
るから長期の放熱により請求項１５の発明による効果を
長期に持続させえる。According to the invention of claim 16, the density difference that allows the circulation of the pressure suppression pool water to be maintained can be reliably maintained for a long period of time, so that the effect of the invention of claim 15 can be maintained for a long period of time due to long-term heat dissipation.
【０１０７】請求項１７の発明によれば、請求項１５又
は請求項１６のいずれかの発明による効果に加えて、放
熱面積が広い割には格納容器を貫通する流路が少なくて
すみ、格納容器の健全性と放熱の向上とを両立できる。According to the invention of claim 17, in addition to the effects of the invention of either claim 15 or 16, the number of flow paths passing through the containment vessel is small in spite of the large heat dissipation area. Both the integrity of the container and the improvement of heat dissipation can be achieved.
【０１０８】請求項１８の発明によれば、原子炉格納容
器壁の広範囲に渡り、水冷による冷却効果の良さを維持
しながらも、格納容器の健全性を維持できるから、より
大出力な原子力プラントに対する原子炉格納容器の圧力
抑制手段として利用できるという効果が得られる。According to the invention of claim 18, it is possible to maintain the integrity of the containment vessel while maintaining the good cooling effect of water cooling over a wide range of the walls of the reactor containment vessel, so that it is possible to maintain the integrity of the containment vessel. This has the effect that it can be used as a means for suppressing pressure in the reactor containment vessel.
【０１０９】請求項１９の発明によれば、請求項１８の
発明による効果に加えて、より一層の原子炉格納容器の
健全性の向上を達成できるし、そのリング状構造物が凝
縮面積を拡大するので冷却効果がより高まり、より一層
の圧力抑制能力が向上する。請求項２０の発明によれば
、請求項１２又は請求項１３又は請求項１４のいずれか
の発明による効果に加えて、請求項１５から請求項１７
のいずれかの発明による効果を重畳させて放熱効果を向
上できる。According to the invention of claim 19, in addition to the effect of the invention of claim 18, the integrity of the reactor containment vessel can be further improved, and the ring-shaped structure expands the condensation area. Therefore, the cooling effect is further enhanced and the pressure suppression ability is further improved. According to the invention of claim 20, in addition to the effect of the invention of claim 12, claim 13, or claim 14,
The heat dissipation effect can be improved by combining the effects of any of the above inventions.
【０１１０】請求項２１の発明によれば、請求項１２又
は請求項１３又は請求項１４のいずれかの発明による効
果に加えて、圧力抑制プール水の対流領域の拡大して鋼
製の壁からの放熱性能の良い領域を拡大させ得るから、
原子炉格納容器の圧力抑制能力が高まる。According to the invention of claim 21, in addition to the effects of the invention of claim 12, claim 13, or claim 14, the convection area of the pressure suppression pool water is expanded and the water is removed from the steel wall. Because it can expand the area with good heat dissipation performance,
The pressure suppression ability of the reactor containment vessel will be increased.
【０１１１】請求項２２の発明によれば、請求項１２又
は請求項１３又は請求項１４又は請求項１５又は請求項
１６又は請求項１７又は請求項２０又は請求項２１のい
ずれかの発明による効果に加えて、原子炉格納容器の健
全性を維持した上で、ウエットウエル冷却水プールでウ
エットウエルも水冷して原子炉格納容器の圧力抑制能力
を高めることが出来る。According to the invention of claim 22, the effect of the invention of claim 12, claim 13, claim 14, claim 15, claim 16, claim 17, claim 20, or claim 21. In addition, while maintaining the integrity of the reactor containment vessel, the wet well can also be water-cooled in the wet well cooling water pool, increasing the pressure suppression ability of the reactor containment vessel.
【０１１２】請求項２３の発明によれば、プール水の許
容温度を圧力抑制室の耐圧の飽和蒸気温度とすることに
より、プールとその外側との温度差を大きくして外側へ
の放熱量を大きくし、大出力の原子力プラントにも採用
できる圧力抑制室を提供できる。According to the invention of claim 23, by setting the allowable temperature of the pool water to the pressure-resistant saturated steam temperature of the pressure suppression chamber, the temperature difference between the pool and the outside thereof is increased and the amount of heat radiated to the outside is increased. It is possible to provide a pressure suppression chamber that can be made larger and adopted in high-output nuclear power plants.
【０１１３】請求項２４の発明によれば、気相の蒸気分
圧の飽和温度から始まる圧力抑制プール水の蒸発を、気
相の全圧力の飽和温度から始まるように変更して、プー
ル水温度をより高い温度で存在できるようにし、プール
とその外側との温度差を大きくして外側への放熱量を大
きくし、大出力の原子力プラントにも採用できる圧力抑
制室を提供できる。According to the invention of claim 24, the pressure suppression pool water evaporation is changed to start from the saturation temperature of the total pressure of the gas phase, so that the evaporation of the pressure suppression pool water starts from the saturation temperature of the vapor partial pressure of the gas phase. This allows the pool to exist at a higher temperature, increases the temperature difference between the pool and the outside, increases the amount of heat released to the outside, and provides a pressure suppression chamber that can be used even in high-output nuclear power plants.
【０１１４】請求項２５の発明によれば、循環流路によ
りプール水を対流させて効率の良い放熱領域を拡大し、
循環流路自体も放熱面となるから、外側への放熱量を大
きくし、大出力の原子力プラントにも採用できる圧力抑
制室を提供できる。According to the twenty-fifth aspect of the invention, the pool water is caused to circulate through the circulation flow path to expand the efficient heat dissipation area,
Since the circulation channel itself also serves as a heat dissipation surface, the amount of heat dissipated to the outside can be increased, and a pressure suppression chamber that can be used even in high-output nuclear power plants can be provided.
【０１１５】請求項２６の発明によれば、プール水の許
容温度を圧力抑制室の耐圧の飽和蒸気温度とすることに
より、プールとその外側との温度差を大きくして外側へ
の放熱量を大きくし、大出力の原子力プラントに適した
圧力抑制方法を提供できる。請求項２７の発明によれば
、プール水の蒸発を気相の全圧力の飽和温度から始まる
ようにし、プール水を高い温度に存在させて、プールと
その外側との温度差を大きくして外側への放熱量を大き
くし、大出力の原子力プラントに適した圧力抑制方法を
提供できる。According to the twenty-sixth aspect of the invention, by setting the allowable temperature of the pool water to the pressure-resistant saturated steam temperature of the pressure suppression chamber, the temperature difference between the pool and the outside thereof is increased and the amount of heat radiated to the outside is increased. It is possible to provide a pressure suppression method suitable for large-scale, high-output nuclear power plants. According to the invention of claim 27, the evaporation of the pool water starts from the saturation temperature of the total pressure of the gas phase, and the pool water is kept at a high temperature to increase the temperature difference between the pool and the outside. It is possible to provide a pressure suppression method suitable for large-output nuclear power plants by increasing the amount of heat dissipated into the reactor.
【０１１６】請求項２８の発明によれば、昇温した上層
のプール水が下層のプール水中へ循環し、プール水中の
温度の均等化を成し、プール水中での蓄熱領域の拡大と
放熱効率の高い領域の拡大とを成し、さらにはそのプー
ル水は循環途中においても冷却して全体として放熱効果
を良くして、大出力の原子力プラントに適した圧力抑制
方法を提供できる。According to the invention of claim 28, the heated upper layer pool water circulates into the lower layer pool water, equalizing the temperature in the pool water, expanding the heat storage area in the pool water, and increasing the heat radiation efficiency. Furthermore, the pool water is cooled even during circulation to improve the overall heat dissipation effect, thereby providing a pressure suppression method suitable for high-output nuclear power plants.
【図１】本発明の実施例による原子炉設備の縦断面図で
ある。FIG. 1 is a longitudinal sectional view of a nuclear reactor equipment according to an embodiment of the present invention.
【図２】図１に示した圧力抑制室及び外周プールの縦断
面を概念的に示した図である。FIG. 2 is a diagram conceptually showing a longitudinal section of the pressure suppression chamber and the peripheral pool shown in FIG. 1;
【図３】本発明の実施例による原子炉格納容器の圧力解
析結果を示したグラフ図である。FIG. 3 is a graph diagram showing pressure analysis results of a reactor containment vessel according to an embodiment of the present invention.
【図４】本発明の他の実施例による圧力抑制室及び外周
プールの縦断面図である。FIG. 4 is a longitudinal sectional view of a pressure suppression chamber and a peripheral pool according to another embodiment of the present invention.
【図５】本発明の更に他の実施例による原子炉設備の縦
断面図である。FIG. 5 is a longitudinal sectional view of a nuclear reactor facility according to still another embodiment of the present invention.
【図６】本発明の他の実施例による原子炉設備の縦断面
図である。FIG. 6 is a longitudinal sectional view of a nuclear reactor equipment according to another embodiment of the present invention.
【図７】図６の実施例による圧力抑制プール及び対流促
進管内の水温・密度分布図である。7 is a water temperature/density distribution diagram in the pressure suppression pool and convection promoting pipe according to the embodiment of FIG. 6; FIG.
【図８】図６の実施例による原子炉格納容器の圧力解析
結果を示したグラフ図である。8 is a graph diagram showing pressure analysis results of the reactor containment vessel according to the embodiment of FIG. 6; FIG.
【図９】本発明の更に他の実施例による圧力抑制室及び
外周プールを示す縦断面図である。FIG. 9 is a longitudinal sectional view showing a pressure suppression chamber and a peripheral pool according to still another embodiment of the present invention.
【図１０】本発明の他の実施例による圧力抑制室及び外
周プールの縦断面図である。FIG. 10 is a longitudinal sectional view of a pressure suppression chamber and a peripheral pool according to another embodiment of the present invention.
【図１１】図１０のＡ−Ａ矢視による圧力抑制室及び外
周プールの一部分の横断面図である。11 is a cross-sectional view of a pressure suppression chamber and a portion of the peripheral pool taken along the line A-A in FIG. 10. FIG.
【図１２】本発明の他の実施例による圧力抑制室及び外
周プールの縦断面図である。FIG. 12 is a longitudinal sectional view of a pressure suppression chamber and a peripheral pool according to another embodiment of the present invention.
【図１３】図１２の実施例による圧力抑制プール及び対
流促進管内の水温・密度分布図である。FIG. 13 is a water temperature/density distribution diagram in the pressure suppression pool and convection promoting pipe according to the embodiment of FIG. 12;
【図１４】本発明の更に他の実施例による圧力抑制室及
び外周プールの縦断面図である。FIG. 14 is a longitudinal sectional view of a pressure suppression chamber and a peripheral pool according to still another embodiment of the present invention.
【図１５】本発明の他の実施例による圧力抑制室及び外
周プールの縦断面図である。FIG. 15 is a longitudinal sectional view of a pressure suppression chamber and a peripheral pool according to another embodiment of the present invention.
【図１６】本発明の更に他の実施例による圧力抑制室及
び外周プールの縦断面図である。FIG. 16 is a longitudinal sectional view of a pressure suppression chamber and a peripheral pool according to still another embodiment of the present invention.
【図１７】本発明の他の実施例による原子炉設備の縦断
面図である。FIG. 17 is a longitudinal sectional view of a nuclear reactor equipment according to another embodiment of the present invention.
【図１８】図１７の実施例による原子炉格納容器の圧力
解析結果を示すグラフ図である。18 is a graph diagram showing the pressure analysis results of the reactor containment vessel according to the embodiment of FIG. 17; FIG.
【図１９】本発明の更に他の実施例による原子炉設備の
縦断面図である。FIG. 19 is a longitudinal sectional view of a nuclear reactor facility according to still another embodiment of the present invention.
【図２０】本発明の他の実施例による原子炉設備の縦断
面図である。FIG. 20 is a longitudinal sectional view of a nuclear reactor facility according to another embodiment of the present invention.
１…炉心、２…原子炉圧力容器、３…ドライウエル、４
…圧力抑制室、５…圧力抑制プール、６…ウエットウエ
ル、７…ベント管、８…原子炉格納容器壁、９…外周プ
ール、１０…上方開口部、１１…下方開口部、１２…対
流促進管、１３…ベント管出口、２１…隔離弁、３１…
上方ヘッダ管、３２…下方ヘッダ管、３３…伝熱管、４
１…ウエットウエル冷却水プール、４２…リング状構造
物、５１…疎水性物質の層、６１…第１空間、６２…第
２空間、６３…区画壁、７０…対流促進板。1...Reactor core, 2...Reactor pressure vessel, 3...Dry well, 4
...Pressure suppression chamber, 5...Pressure suppression pool, 6...Wet well, 7...Vent pipe, 8...Reactor containment vessel wall, 9...Outer peripheral pool, 10...Upper opening, 11...Lower opening, 12...Convection promotion Pipe, 13...Vent pipe outlet, 21...Isolation valve, 31...
Upper header pipe, 32... Lower header pipe, 33... Heat exchanger tube, 4
DESCRIPTION OF SYMBOLS 1... Wet well cooling water pool, 42... Ring-shaped structure, 51... Hydrophobic substance layer, 61... First space, 62... Second space, 63... Partition wall, 70... Convection promotion plate.
Claims (28)
子炉圧力容器が配備されたドライウエルと、前記ドライ
ウエルを収納した格納容器と、プール水領域とドライウ
エル空間とから成る圧力抑制室と、前記ドライウエルと
前記プール水中とを連通する流路とを備えた原子炉格納
容器において、前記圧力抑制室のウエットウエルに連通
して他の室を備え、前記他の室は原子炉の冷却材喪失事
故時に前記プール水を包含する室よりも低温の条件下と
成る位置に配置されていることを特徴とした原子炉格納
容器。Claim 1: A pressure suppression system comprising a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, a pool water area, and a dry well space. A reactor containment vessel comprising a chamber and a flow path communicating the dry well and the pool water, further comprising another chamber communicating with the wet well of the pressure suppression chamber, the other chamber being connected to the reactor. A nuclear reactor containment vessel, characterized in that the reactor containment vessel is located at a position where the temperature is lower than that of the chamber containing the pool water in the event of a loss of coolant accident.
プール水を包含する室と他の室とに分けて、前記他の室
は原子炉の冷却材喪失事故時に前記プール水を包含する
室よりも低温の条件下と成る位置に配置されていること
を特徴とした原子炉格納容器である。2. In claim 1, the pressure suppression chamber is divided into a chamber containing the pool water and another chamber, the other chamber containing the pool water in the event of a reactor loss of coolant accident. A nuclear reactor containment vessel characterized by being located at a location where conditions are lower than that of the reactor containment vessel.
少なくとも圧力抑制室のプール水領域が前記プール水と
内面において接する鋼製の壁により構成され、前記鋼製
の壁の外周面に接して外周プールを備えていることを特
徴とした原子炉格納容器。3. According to claim 1 or 2, the containment vessel is constituted by a steel wall in which at least a pool water region of the pressure suppression chamber is in contact with the pool water on an inner surface, and the containment vessel is in contact with an outer circumferential surface of the steel wall. A nuclear reactor containment vessel characterized by being equipped with a peripheral pool.
子炉圧力容器が配備されたドライウエルと、前記ドライ
ウエルを収納した格納容器と、プール水領域とドライウ
エル空間とから成る圧力抑制室と、前記ドライウエルと
前記プール水中とを連通する流路とを備えた原子炉格納
容器において、前記流路の前記プール水への出口よりも
高い位置に取水口が、同じく低い位置に排水口が前記プ
ールス水中に開かれた循環流路を備え、前記循環流路は
少なくとも一部が前記格納容器の外側に通されているこ
とを特徴とした原子炉格納容器。4. A pressure suppression system comprising a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, a pool water area, and a dry well space. A reactor containment vessel comprising a chamber and a channel communicating between the dry well and the pool water, wherein a water intake is located at a higher position than the outlet of the channel to the pool water, and a water outlet is located at a lower location as well. A nuclear reactor containment vessel, comprising a circulation flow path having an opening opened into the pool water, and at least a portion of the circulation flow path passing outside the containment vessel.
冷却手段を備えたことを特徴とした原子炉格納容器。5. The reactor containment vessel according to claim 4, further comprising a cooling means in the middle of the circulation flow path.
子炉圧力容器が配備されたドライウエルと、前記ドライ
ウエルを収納した格納容器と、プール水領域とドライウ
エル空間とから成る圧力抑制室と、前記ドライウエルと
前記プール水中とを連通する流路とを備えた原子炉格納
容器において、前記流路の前記プール水への出口よりも
高い位置のプール水を同じく低い位置のプール水中に循
環させる循環流路を備え、前記循環流路は少なくとも一
部が前記格納容器の外側に通されていることを特徴とし
た原子炉格納容器。6. A pressure suppression system comprising a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, a pool water area, and a dry well space. In a reactor containment vessel, the reactor containment vessel includes a flow path communicating between the dry well and the pool water, the pool water at a higher position than the outlet of the flow path to the pool water is connected to the pool water at a lower position as well. A nuclear reactor containment vessel, comprising a circulation flow path for causing circulation, and at least a portion of the circulation flow path passes outside the containment vessel.
冷却手段を備えたことを特徴とした原子炉格納容器。7. The reactor containment vessel according to claim 6, further comprising a cooling means in the middle of the circulation flow path.
子炉圧力容器が配備されたドライウエルと、前記ドライ
ウエルを収納した格納容器と、プール水領域とドライウ
エル空間とから成る圧力抑制室と、前記ドライウエルと
前記プール水中とを連通する流路とを備えた原子炉格納
容器において、前記圧力抑制室に蒸気流体と他の流体と
の分別収集手段を装備したことを特徴とした原子炉格納
容器。8. A pressure suppression system comprising a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, a pool water area, and a dry well space. A nuclear reactor containment vessel comprising a chamber and a flow path communicating between the dry well and the pool water, characterized in that the pressure suppression chamber is equipped with means for separating and collecting steam fluid and other fluids. Reactor containment vessel.
とも圧力抑制室のプール水領域が前記プール水と内面に
おいて接する鋼製の壁により構成され、前記鋼製の壁の
外周面に対する冷却手段を備えていることを特徴とした
原子炉格納容器。9. In claim 8, the containment vessel is constituted by a steel wall in which at least a pool water region of the pressure suppression chamber is in contact with the pool water on an inner surface, and cooling means is provided for the outer circumferential surface of the steel wall. A nuclear reactor containment vessel characterized by:
原子炉圧力容器が配備されたドライウエルと、前記ドラ
イウエルを収納した格納容器と、プール水領域とドライ
ウエル空間とから成る圧力抑制室と、前記ドライウエル
と前記プール水中とを連通する流路とを備えた原子炉格
納容器において、前記プール水の水面上方に前記プール
水の蒸発抑制手段を備えたことを特徴とした原子炉格納
容器。10. A pressure suppression system comprising a reactor pressure vessel containing a reactor core, a dry well in which the reactor pressure vessel is installed, a containment vessel housing the dry well, a pool water area, and a dry well space. A reactor containment vessel comprising a chamber and a flow path communicating between the dry well and the pool water, the reactor comprising: evaporation suppressing means for the pool water above the water surface of the pool water. Containment vessel.
なくとも圧力抑制室のプール水領域が前記プール水と内
面において接する鋼製の壁により構成され、前記鋼製の
壁の外周面に対する冷却手段を備えていることを特徴と
した原子炉格納容器。11. In claim 10, the containment vessel is constituted by a steel wall in which at least a pool water region of the pressure suppression chamber is in contact with the pool water on an inner surface, and cooling means is provided for an outer peripheral surface of the steel wall. A nuclear reactor containment vessel characterized by:
れたドライウエルと、圧力抑制プール水を保有する圧力
抑制室と、前記ドライウエルと前記圧力抑制プール水中
を連通するベント管と、前記圧力抑制プール水に接して
前記圧力抑制プール水の外周囲を囲う鋼製の壁と、前記
壁の外周面に接して冷却水を内蔵出来る外周プールとを
備えた原子炉格納容器において、前記圧力抑制室内の圧
力抑制プール上方に位置するウェットウエルを、前記圧
力抑制プール水の水面と接する領域とそうでない領域に
区画し、前記両領域を前記区画面よりも狭い面積の流路
で連通するとともに、圧力抑制プール水水面に接しない
領域を冷却する手段を備えたことを特徴とした原子炉格
納容器。12. A dry well provided with a reactor pressure vessel containing a reactor core, a pressure suppression chamber holding pressure suppression pool water, a vent pipe communicating the dry well with the pressure suppression pool water, and the In a reactor containment vessel, the reactor containment vessel includes a steel wall that is in contact with pressure suppression pool water and surrounds the outer periphery of the pressure suppression pool water, and an outer peripheral pool that is in contact with the outer peripheral surface of the wall and can contain cooling water. A wet well located above the pressure suppression pool in the suppression chamber is divided into an area in contact with the water surface of the pressure suppression pool and an area not in contact with the water surface of the pressure suppression pool, and both areas are communicated by a flow path having an area narrower than the partition surface. , a reactor containment vessel characterized by being equipped with means for cooling an area not in contact with the pressure suppression pool water surface.
いて、圧力抑制プール水水面に接しない領域の下部と圧
力抑制プール水中を連通する流路を設けたことを特徴と
した原子炉格納容器。13. The reactor containment vessel according to claim 12, wherein a flow path is provided that communicates the lower part of the area not in contact with the pressure suppression pool water surface with the pressure suppression pool water. .
れたドライウエルと、圧力抑制プール水を保有する圧力
抑制室と、前記ドライウエルと前記圧力抑制プール水中
を連通するベント管と、前記圧力抑制プール水に接して
前記圧力抑制プール水の外周囲を囲う鋼製の壁と、前記
壁の外周面に接して冷却水を内蔵出来る外周プールとを
備えた原子炉格納容器において、前記圧力抑制プール水
水面に、前記圧力抑制プール水よりも飽和蒸気圧が低く
、かつ密度が小さい疎水性物質の層を形成したことを特
徴とした原子炉格納容器。14. A dry well provided with a reactor pressure vessel containing a reactor core, a pressure suppression chamber holding pressure suppression pool water, a vent pipe communicating the dry well with the pressure suppression pool water, and the In a reactor containment vessel, the reactor containment vessel includes a steel wall that is in contact with pressure suppression pool water and surrounds the outer periphery of the pressure suppression pool water, and an outer peripheral pool that is in contact with the outer peripheral surface of the wall and can contain cooling water. A nuclear reactor containment vessel characterized in that a layer of a hydrophobic substance having a lower saturated vapor pressure and a lower density than the pressure suppression pool water is formed on the water surface of the suppression pool.
れたドライウエルと、圧力抑制プール水を保有する圧力
抑制室と、前記ドライウエルと前記圧力抑制プール水中
を連通するベント管と、前記圧力抑制プール水に接して
前記圧力抑制プール水の外周囲を囲う鋼製の壁と、前記
壁の外周面に接して冷却水を内蔵出来る外周プールとを
備えた原子炉格納容器において、前記圧力抑制プール水
水面下方にて前記ベント管の出口高さの上下となる各位
置で前記圧力抑制プール水中に開かれたそれぞれ少なく
とも一つ以上の開口部を有し、前記上下の各開口部を上
下方向に連結して内部に前記圧力抑制プール水が通る対
流促進管が前記外周プール内にあることを特徴とした原
子炉格納容器。15. A dry well provided with a reactor pressure vessel containing a reactor core, a pressure suppression chamber holding pressure suppression pool water, a vent pipe communicating the dry well with the pressure suppression pool water, and the In a reactor containment vessel, the reactor containment vessel includes a steel wall that is in contact with pressure suppression pool water and surrounds the outer periphery of the pressure suppression pool water, and an outer peripheral pool that is in contact with the outer peripheral surface of the wall and can contain cooling water. At least one or more openings are opened into the pressure suppression pool water at positions above and below the outlet height of the vent pipe below the suppression pool water surface, and each of the upper and lower openings is connected to the upper and lower openings. A nuclear reactor containment vessel characterized in that a convection promoting pipe is provided in the outer circumferential pool and is connected in the direction of the pressure suppression pool and through which the pressure suppression pool water passes.
と前記ベント管の出口との高さの差が、前記ベント管の
出口と前記下方の開口部との高さの差より大きいことを
特徴とした原子炉格納容器。16. In claim 15, the difference in height between the upper opening and the outlet of the vent pipe is greater than the difference in height between the outlet of the vent pipe and the lower opening. Featured reactor containment vessel.
記外周プール内に上下に分けて夫々配備されたヘッダ管
と、前記上方のヘッダ管と前記下方のヘッダ管とを連通
する複数の伝熱管とによって前記対流促進管を構成した
ことを特徴とした原子炉格納容器。17. According to claim 15 or 16, header pipes are arranged in upper and lower parts in the outer circumferential pool, and a plurality of heat transfer pipes communicate with the upper header pipe and the lower header pipe. A nuclear reactor containment vessel characterized in that the convection promoting tube is configured by:
れたドライウエルと、圧力抑制プール水を保有する圧力
抑制室と、前記ドライウエルと前記圧力抑制プール水中
を連通するベント管と、前記圧力抑制室の外周囲を囲う
鋼製の壁と、前記圧力抑制プール水に対応する前記壁の
外周面に接して冷却水を内蔵出来る外周プールとを備え
た原子炉格納容器において、前記外周プールの冷却水水
面よりも高い位置で前記壁に接する他の冷却水を内蔵で
きるウェットウエル冷却水プールを前記外周プールとは
独立に備えることを特徴とした原子炉格納容器。18. A dry well provided with a reactor pressure vessel containing a reactor core, a pressure suppression chamber holding pressure suppression pool water, a vent pipe communicating the dry well with the pressure suppression pool water, and the In a reactor containment vessel comprising a steel wall surrounding an outer periphery of a pressure suppression chamber, and an outer peripheral pool that can contain cooling water in contact with the outer peripheral surface of the wall corresponding to the pressure suppression pool water, the outer peripheral pool A nuclear reactor containment vessel, comprising: a wet well cooling water pool that can contain other cooling water and is in contact with the wall at a higher position than the cooling water surface of the outer peripheral pool, and is independent of the outer peripheral pool.
いて、前記ウェットウエル冷却水プールに対応する前記
圧力抑制室内の前記壁にリング状構造物を備えたことを
特徴とした原子炉格納容器。19. The reactor containment vessel according to claim 18, wherein a ring-shaped structure is provided on the wall in the pressure suppression chamber corresponding to the wet well cooling water pool. .
４において、請求項１５から請求項１７までのいずれか
１項に記載の対流促進管を備えたことを特徴とした原子
炉格納容器。Claim 20: Claim 12 or Claim 13 or Claim 1
4, a nuclear reactor containment vessel comprising the convection promoting tube according to any one of claims 15 to 17.
４において、前記鋼製の壁に沿って圧力抑制プール水中
にあり、その上端が前記ベント管の出口より高い位置に
、その下端がベント管の出口よりも低い位置に成る高さ
関係であり、前記上端と前記ベント管の出口の高さの差
を前記ベント管の出口と前記下端の高さの差より大きく
して配備した対流促進板を備えていることを特徴とした
原子炉格納容器。Claim 21: Claim 12 or Claim 13 or Claim 1
4, the pressure suppression pool is located underwater along the steel wall, and has a height relationship such that its upper end is at a higher position than the outlet of the vent pipe, and its lower end is at a position lower than the outlet of the vent pipe, A nuclear reactor containment vessel comprising a convection promoting plate arranged such that the difference in height between the upper end and the outlet of the vent pipe is greater than the difference in height between the outlet of the vent pipe and the lower end.
４又は請求項１５又は請求項１６又は請求項１７又は請
求項２０又は請求項２１において、請求項１８に記載の
ウェットウエル冷却水プール又は請求項１９に記載のウ
ェットウエル冷却水プールとリング状構造物を備えたこ
とを特徴とした原子炉格納容器。Claim 22: Claim 12 or Claim 13 or Claim 1
4 or claim 15 or claim 16 or claim 17 or claim 20 or claim 21, the wet well cooling water pool according to claim 18 or the wet well cooling water pool according to claim 19 and a ring-shaped structure A nuclear reactor containment vessel characterized by being equipped with objects.
領域とから成り、前記プール水領域中に蒸気の吐出口を
臨ませてある圧力抑制室において、前記気相領域に少な
くとも一部分が冷却環境下に配備された他室を前記プー
ル水の蒸発面積より狭い流路面積の流路を通じて連通し
てあることを特徴とした圧力抑制室。23. A pressure suppression chamber comprising a pool water region and a gas phase region in contact with the pool water region, the pressure suppression chamber having a steam discharge port facing into the pool water region, wherein at least a portion of the gas phase region is cooled. A pressure suppression chamber, characterized in that other chambers arranged in the environment are communicated through a channel having a channel area smaller than the evaporation area of the pool water.
領域とから成り、前記プール水領域中に蒸気の吐出口を
臨ませてある圧力抑制室において、前記プール水の水面
上方に前記プール水の蒸発抑制手段を備えたことを特徴
とした圧力抑制室。24. A pressure suppression chamber comprising a pool water region and a gas phase region in contact with the pool water region, the pressure suppression chamber having a steam discharge port facing into the pool water region, wherein the pressure suppression chamber is arranged above the water surface of the pool water. A pressure suppression chamber characterized by being equipped with water evaporation suppression means.
領域とから成り、前記プール水領域中に蒸気の吐出口を
臨ませてある圧力抑制室において、前記吐出口よりも高
い位置の前記プール水を同じく低い位置のプール水中に
循環させる循環流路を備え、前記循環流路は少なくとも
一部が前記圧力抑制室の圧力抑制機能が成されていると
きの前記圧力抑制室中の前記プール水温度よりも低温の
環境下に通されていることを特徴とした圧力抑制室。25. In a pressure suppression chamber comprising a pool water region and a gas phase region in contact with the region, and having a steam discharge port facing into the pool water region, the pressure suppression chamber is located at a position higher than the discharge port. A circulation flow path is provided for circulating pool water into the pool water at a lower position, and the circulation flow path is arranged at least partially in the pool in the pressure suppression chamber when the pressure suppression function of the pressure suppression chamber is performed. A pressure suppression chamber characterized by being passed through an environment at a temperature lower than that of water.
室内のプール水中に放出して凝縮し、前記凝縮による前
記プール水中の蓄熱を前記原子炉格納容器外へ排出する
方法において、前記圧力抑制室内の不凝縮性気体と前記
プール水からの蒸気との混合流体を前記不凝縮性気体と
前記プール水からの蒸気とに分別し、前記分別後の蒸気
を前記プール水を包含する区画に残存させ、前記分別後
の不凝縮気体を前記区画とは流通自在な他の区画に収集
することを特徴とした原子炉格納容器内の圧力抑制方法
。26. A method for releasing leaked steam in a reactor containment vessel into pool water in a pressure suppression chamber and condensing it, and discharging heat accumulated in the pool water due to the condensation to the outside of the reactor containment vessel, wherein the pressure A mixed fluid of non-condensable gas and steam from the pool water in a suppression chamber is separated into the non-condensable gas and steam from the pool water, and the separated steam is transferred to a compartment containing the pool water. 1. A method for suppressing pressure in a reactor containment vessel, characterized in that the non-condensable gas remaining after the separation is collected in a section other than the section through which it can freely flow.
室内のプール水中に放出して凝縮し、前記凝縮による前
記プール水中の蓄熱を前記原子炉格納容器外へ排出する
方法において、前記プール水の沸騰前においては前記プ
ール水と前記圧力抑制室内気相空間との接触を断ち、前
記プール水の沸騰によって前記プール水から前記圧力抑
制室内気相空間への蒸気移行を行うとにより前記プール
水の蒸発開始を圧力抑制室気相空間の蒸気分圧の飽和温
度から前記圧力抑制室気相空間の全圧力の飽和温度に変
えたことを特徴とした原子炉格納容器内の圧力抑制方法
。27. A method for releasing leaked steam in the reactor containment vessel into pool water in a pressure suppression chamber and condensing it, and discharging heat accumulated in the pool water due to the condensation to the outside of the reactor containment vessel, Before the water boils, the contact between the pool water and the gas phase space in the pressure suppression chamber is cut off, and the boiling of the pool water causes vapor transfer from the pool water to the gas phase space in the pressure suppression chamber. A method for suppressing pressure in a nuclear reactor containment vessel, characterized in that the start of evaporation of water is changed from the saturation temperature of the partial pressure of steam in the gas phase space of the pressure suppression chamber to the saturation temperature of the total pressure in the gas phase space of the pressure suppression chamber.
室内のプール水中に放出して凝縮し、前記凝縮による前
記プール水中の蓄熱を前記原子炉格納容器外へ排出する
方法において、前記圧力抑制室への前記蒸気の放出位置
の高さよりも高い位置の前記プール水の領域と前記蒸気
の放出位置の高さよりも低い位置の前記プール水領域と
を連通し、前記連通途中の前記プール水を冷却して温度
依存による密度を高めて前記蒸気の放出位置の高さより
も高い位置の前記プール水の領域から前記蒸気の放出位
置の高さよりも低い位置の前記プール水領域への循環駆
動力を得ることを特徴とした原子炉格納容器内の圧力抑
制方法。28. A method for releasing leaked steam in a reactor containment vessel into pool water in a pressure suppression chamber and condensing it, and discharging heat accumulated in the pool water due to the condensation to the outside of the reactor containment vessel, wherein the pressure A region of the pool water at a position higher than the height of the steam release position to the suppression chamber and a pool water region at a position lower than the height of the steam release position are communicated, and the pool water is in the middle of the communication. by cooling the pool water to increase its temperature-dependent density to circulate the driving force from the pool water area at a position higher than the height of the steam release position to the pool water area at a position lower than the height of the steam release position. A method for suppressing pressure in a nuclear reactor containment vessel, characterized by obtaining the following:
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3056300A JP2701564B2 (en) | 1991-03-20 | 1991-03-20 | Reactor containment vessel |
| US07/775,850 US5295169A (en) | 1990-10-15 | 1991-10-15 | Reactor containment facilities |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3056300A JP2701564B2 (en) | 1991-03-20 | 1991-03-20 | Reactor containment vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH04290994A true JPH04290994A (en) | 1992-10-15 |
| JP2701564B2 JP2701564B2 (en) | 1998-01-21 |
Family
ID=13023274
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP3056300A Expired - Fee Related JP2701564B2 (en) | 1990-10-15 | 1991-03-20 | Reactor containment vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2701564B2 (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0599614A1 (en) * | 1992-11-25 | 1994-06-01 | General Electric Company | Passive containment cooling system |
| US6618461B2 (en) * | 2001-02-12 | 2003-09-09 | General Electric Company | Systems and methods to enhance passive containment cooling system |
| WO2012073411A1 (en) * | 2010-11-29 | 2012-06-07 | 株式会社 東芝 | Nuclear reactor containment vessel and nuclear power plant |
| JP2014055947A (en) * | 2012-09-12 | 2014-03-27 | Ge-Hitachi Nuclear Energy Americas Llc | Method and system for alternative bwr containment heat removal |
| JP2015203565A (en) * | 2014-04-10 | 2015-11-16 | 日立Ｇｅニュークリア・エナジー株式会社 | Static nuclear reactor containment cooling system and nuclear power plant |
| CN105654996A (en) * | 2014-12-01 | 2016-06-08 | 上海核工程研究设计院 | Safe bunker structure of reactor |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0296689A (en) * | 1988-10-04 | 1990-04-09 | Hitachi Ltd | Containment vessel in nuclear reactor |
| JPH02176496A (en) * | 1988-11-16 | 1990-07-09 | Hitachi Ltd | Reactor container |
-
1991
- 1991-03-20 JP JP3056300A patent/JP2701564B2/en not_active Expired - Fee Related
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0296689A (en) * | 1988-10-04 | 1990-04-09 | Hitachi Ltd | Containment vessel in nuclear reactor |
| JPH02176496A (en) * | 1988-11-16 | 1990-07-09 | Hitachi Ltd | Reactor container |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0599614A1 (en) * | 1992-11-25 | 1994-06-01 | General Electric Company | Passive containment cooling system |
| US6618461B2 (en) * | 2001-02-12 | 2003-09-09 | General Electric Company | Systems and methods to enhance passive containment cooling system |
| WO2012073411A1 (en) * | 2010-11-29 | 2012-06-07 | 株式会社 東芝 | Nuclear reactor containment vessel and nuclear power plant |
| JP2012117821A (en) * | 2010-11-29 | 2012-06-21 | Toshiba Corp | Reactor containment vessel and nuclear power plant |
| CN103229246A (en) * | 2010-11-29 | 2013-07-31 | 株式会社东芝 | Nuclear reactor containment vessel and nuclear power plant |
| US9818495B2 (en) | 2010-11-29 | 2017-11-14 | Kabushiki Kaisha Toshiba | Containment vessel and nuclear power plant |
| JP2014055947A (en) * | 2012-09-12 | 2014-03-27 | Ge-Hitachi Nuclear Energy Americas Llc | Method and system for alternative bwr containment heat removal |
| JP2015203565A (en) * | 2014-04-10 | 2015-11-16 | 日立Ｇｅニュークリア・エナジー株式会社 | Static nuclear reactor containment cooling system and nuclear power plant |
| CN105654996A (en) * | 2014-12-01 | 2016-06-08 | 上海核工程研究设计院 | Safe bunker structure of reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2701564B2 (en) | 1998-01-21 |
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