JPH0259697A - Boiling water reactor - Google Patents
Boiling water reactorInfo
- Publication number
- JPH0259697A JPH0259697A JP63209420A JP20942088A JPH0259697A JP H0259697 A JPH0259697 A JP H0259697A JP 63209420 A JP63209420 A JP 63209420A JP 20942088 A JP20942088 A JP 20942088A JP H0259697 A JPH0259697 A JP H0259697A
- Authority
- JP
- Japan
- Prior art keywords
- chimney
- water level
- reactor
- pressure vessel
- core
- 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.)
- Pending
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 46
- 238000009835 boiling Methods 0.000 title claims description 7
- 230000007704 transition Effects 0.000 abstract description 2
- 238000007562 laser obscuration time method Methods 0.000 abstract 2
- 239000002826 coolant Substances 0.000 description 13
- 230000001052 transient effect Effects 0.000 description 5
- 230000000694 effects Effects 0.000 description 3
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000004927 fusion Effects 0.000 description 1
- 239000007787 solid Substances 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
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は、気水分離器を使用しない自然循環型の沸騰水
型原子炉に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a natural circulation boiling water nuclear reactor that does not use a steam/water separator.
（従来の技術）
以下、第４図を参照して気水分離器を使用しない自然循
環型の沸騰水型原子炉（以下ＢＷＲと略す）の従来例を
説明する。(Prior Art) Hereinafter, a conventional example of a natural circulation boiling water reactor (hereinafter abbreviated as BWR) that does not use a steam-water separator will be described with reference to FIG.
第４図において、原子炉圧力容器１内にはシュラウド２
が配設されている。このシュラウド２の上方は開放され
、内部には炉心３が収容されている。この炉心３は燃料
集合体４と制御棒５を格子状、に配列して構成しており
、上部を」二部格子板６、下部を炉心支持板７によって
支持されている。なお、前記制御棒５は前記炉心３の下
方に配設された制御棒案内管８内を収納自在に移動する
構成になっている。この制御棒案内管８の下部には前記
制御棒５を駆動させる制御棒駆動機構９及び制御棒駆動
機構ハウジング１０が配設されている。前記シュラウド
２の上部には炉心３にて発生した湿分の多い蒸気から湿
分を取り除く蒸気乾燥器１１が配設されている。さらに
シュラウド２の側部には給水スパージャ１２が配設され
ている。In FIG. 4, there is a shroud 2 inside the reactor pressure vessel 1.
is installed. The upper part of this shroud 2 is open, and the reactor core 3 is housed inside. This core 3 is constructed by arranging fuel assemblies 4 and control rods 5 in a lattice pattern, and is supported by a two-part lattice plate 6 at the top and a core support plate 7 at the bottom. The control rods 5 are configured to move within a control rod guide tube 8 disposed below the reactor core 3 so as to be freely retractable. A control rod drive mechanism 9 for driving the control rod 5 and a control rod drive mechanism housing 10 are disposed below the control rod guide tube 8. A steam dryer 11 is disposed above the shroud 2 to remove moisture from the humid steam generated in the reactor core 3. Further, a water supply sparger 12 is disposed on the side of the shroud 2.
以上の構成において、ＢＷＲの第４図中矢印で示す循環
流の駆動力は炉心ｊ下端より上方のシュラウド２内外の
冷却材の密度差によって得られる。In the above configuration, the driving force of the circulating flow shown by the arrow in FIG. 4 of the BWR is obtained by the density difference between the coolant inside and outside the shroud 2 above the lower end of the core j.
このシュラウド２内における冷却材の密度差は、炉心３
から発生する熱によって冷却材が水−蒸気の二相流にな
り、蒸気分の密度の低減によって生ずる。従って、炉心
３下端からシュラウド２の上端までの距離が大きいほど
、大きな駆動力が得られる。なお、炉心３より下方では
シュラウド２内外で冷却材の密度差が生じないので、駆
動力には寄与しない。This difference in coolant density within the shroud 2
The heat generated from the coolant transforms the coolant into a two-phase water-steam flow, resulting from a reduction in the density of the steam component. Therefore, the greater the distance from the lower end of the core 3 to the upper end of the shroud 2, the greater the driving force can be obtained. Note that since there is no difference in the density of the coolant between the inside and outside of the shroud 2 below the core 3, it does not contribute to the driving force.
通常水位の設定は通常運転時の必要な炉心流量を確保す
るとともに主蒸気融離弁（図示せず）閉鎖等の過渡時に
気相部の圧力上昇により冷却材中の気泡がつぶれ水位が
低下した場合でも、その水位がシュラウドの上端より上
方にあり、自然循環流が断たれることなく、炉心の冷却
が可能となる様に水位Ａの位置に設定されている。すな
わち、シュラウド上端から上の冷却材は自然循環流の駆
動力に寄与しないため、シュラウド上端が水没していな
いとシュラウド上端から外側面に冷却材が流入せず、循
環流の流れが断たれ炉心の冷却が困難となる可能性があ
る。The normal water level is set to ensure the necessary core flow rate during normal operation, and also to ensure that during transients such as when the main steam fusion valve (not shown) is closed, the pressure in the gas phase increases, causing bubbles in the coolant to collapse and the water level to drop. Even if the water level is higher than the upper end of the shroud, the water level is set at level A so that the core can be cooled without interrupting the natural circulation flow. In other words, the coolant above the top of the shroud does not contribute to the driving force of the natural circulation flow, so if the top of the shroud is not submerged, coolant will not flow from the top of the shroud to the outer surface, cutting off the circulation flow and damaging the core. cooling may become difficult.
（発明が解決しようとする課題）
上述したように、過渡時に冷却材中の気泡がつぶれ、水
位が低下した場合でも、自然循環流が断たれることの無
いよう水位が設定されているので、通常水位が炉内の高
い位置に設定されている。このため、原子炉圧力容器の
高さが高くなり、原子炉圧力容器の縮小化が望まれてい
た。(Problem to be Solved by the Invention) As mentioned above, even if the bubbles in the coolant collapse during a transient period and the water level drops, the water level is set so that the natural circulation flow will not be cut off. Normally the water level is set high in the furnace. For this reason, the height of the reactor pressure vessel has increased, and it has been desired to downsize the reactor pressure vessel.
本発明の目的は、過渡時に原子炉水位が低下した場合に
おいても、自然循環流が断たれることがなく、炉心の冷
却が可能でかつ原子炉圧力容器の高さを低くすることの
できるＢＷＲを得ることにある。The purpose of the present invention is to provide a BWR that can cool the reactor core without cutting off the natural circulation flow even when the reactor water level drops during a transient period, and that can reduce the height of the reactor pressure vessel. It's about getting.
（課題を解決するための手段）
上記目的を達成するために、本発明においては、原子炉
圧力容器内に配設され上方に開口部が形成されて成る下
部チムニと、この下部チムニ内に収容された炉心と、こ
の下部チムニの上端を囲繞し上端開口部を運転水位より
下方に形成した上部チムニと、この上部チムニの上方に
配設された蒸気乾燥器と、前記下部チムニの上端より下
方に開口を配設した給水スパージャとから成ることを特
徴とするＢＷＲを提供する。(Means for Solving the Problems) In order to achieve the above object, the present invention provides a lower chimney arranged in a reactor pressure vessel and having an opening formed above, and a an upper chimney that surrounds the upper end of the lower chimney and has an upper end opening below the operating water level; a steam dryer disposed above the upper chimney; The present invention provides a BWR characterized by comprising a water supply sparger having an opening at the bottom of the water supply sparger.
（作 用）
このように構成されたＢＷＲにおいては、原子炉水位が
低下し、通常運転時に冷却材が循環する上部チムニ上部
に形成された経路が断たれた場合でも、上部チムニと下
部チムニとの間に形成された循環経路によって冷却材の
循環を確保することができる。よって１通常運転水位を
下げることができるので、原子炉圧力容器高さを低くす
ることができる。(Function) In a BWR configured in this way, even if the reactor water level drops and the path formed above the upper chimney through which coolant circulates during normal operation is cut off, the upper chimney and lower chimney will remain connected. Circulation of the coolant can be ensured by the circulation path formed between the two. Therefore, the normal operation water level can be lowered, so the height of the reactor pressure vessel can be lowered.
（実施例）
以下１本発明の第１実施例に係るＢＷＲを第１図を参照
して説明する。なお、第１図において、第４図と同一部
分には同一符号を付し、その部分の構成の説明は省略す
る。第１図において、原子炉圧力容器１内には炉心３を
収容する下部チムニ１３が配設されている。この下部チ
ムニ１３内には上部格子板６及び炉心支持板７が配設さ
れており、その上端は過渡時に炉心３内の気泡がつぶれ
水位が最も低下した場合でも水没している位置に設定さ
れている。この下部チムニ１３の上部には上部チムニ１
４が配設されている。この上部チムニ１４の上端は自然
循環流の必要流量が十分得られる位置に設定され、この
上部チムニ上端と蒸気乾燥器１１の下端は一部重複した
位置になっている。そして、この構成によって炉心３か
ら発生した蒸気が前記下部チムニ１３と原子炉圧力容器
１によって形成されたダウンカマ１５に漏洩させないよ
うに成っている。この上部チムニ１４の下端は下部チム
ニ１３の上端を囲包して形成され、この上部チムニ１４
と下部チムニ１３との間ＶＸ１６によって過渡時の自然
循環流が確保されている。また、通常運転時は、上・下
部チムニ１３．１４内の圧力がダウンカマ１５より低く
、ダウンカマ１５の冷却水が間隙１６から上・下部チム
ニ１３．１４内に流入するのを防ぐために、上部チムニ
１４下端の下方である原子炉圧力容器１の内壁に給水ス
パージャ１７を設置し、給水を噴射させることによって
水シールを作っている。(Embodiment) A BWR according to a first embodiment of the present invention will be described below with reference to FIG. In FIG. 1, the same parts as in FIG. 4 are given the same reference numerals, and the explanation of the structure of the parts will be omitted. In FIG. 1, a lower chimney 13 for accommodating a reactor core 3 is disposed within a reactor pressure vessel 1. An upper lattice plate 6 and a core support plate 7 are disposed within this lower chimney 13, and their upper ends are set at a position where they remain submerged in water even when the bubbles in the core 3 are collapsed during transients and the water level is at its lowest. ing. Above this lower chimney 13 is an upper chimney 1.
4 are arranged. The upper end of this upper chimney 14 is set at a position where the required flow rate of the natural circulation flow can be sufficiently obtained, and the upper end of this upper chimney and the lower end of the steam dryer 11 are in a position where they partially overlap. This configuration prevents steam generated from the reactor core 3 from leaking into the downcomer 15 formed by the lower chimney 13 and the reactor pressure vessel 1. The lower end of this upper chimney 14 is formed to surround the upper end of the lower chimney 13, and this upper chimney 14
A natural circulation flow during transient periods is ensured by the VX16 between the lower chimney 13 and the lower chimney 13. In addition, during normal operation, the pressure inside the upper and lower chimneys 13.14 is lower than that of the downcomer 15, and in order to prevent the cooling water of the downcomer 15 from flowing into the upper and lower chimneys 13.14 from the gap 16, the upper chimney A water supply sparger 17 is installed on the inner wall of the reactor pressure vessel 1 below the lower end of the reactor pressure vessel 1, and a water seal is created by injecting water supply.
以上の構成において、通常運転時は図中で示す水位がＢ
の位置となっている。よって自然循環流は図中の実線の
矢印方向に流れる。そして、過渡時に冷却材中の気泡が
つぶれ水位が低下し破線Ｃの位置になった場合は、自然
循環流が破線の矢印りの様に流れる。よって通常水位を
上部チムニ１４よりわずか上方に設定した場合において
も過渡の炉水位低下時の自然循環流が確保できるので、
通常水位を低い位置に設定することができる。よって、
水位を下げられる分だけ原子炉圧力容器の高さを小さく
することができる。In the above configuration, during normal operation, the water level shown in the diagram is B
It is located at Therefore, the natural circulation flow flows in the direction of the solid arrow in the figure. During the transition, when the bubbles in the coolant collapse and the water level drops to the position indicated by broken line C, a natural circulation flow flows as indicated by the broken line arrow. Therefore, even if the normal water level is set slightly above the upper chimney 14, natural circulation flow can be ensured during a transient decrease in the reactor water level.
Normally, the water level can be set at a low position. Therefore,
The height of the reactor pressure vessel can be reduced by the amount that the water level can be lowered.
次に、本発明の第２実施例を第２図および第３図を参照
して説明する。なお、第２図および第３図において、第
１図と同一部分には同一符号を付し、その部分の構成の
説明を省略する。Next, a second embodiment of the present invention will be described with reference to FIGS. 2 and 3. In FIGS. 2 and 3, the same parts as in FIG. 1 are given the same reference numerals, and explanations of the configurations of those parts will be omitted.
第２図において、上部チムニ１４と下部チムニ１３とに
て形成される環状の間隙１６に給水スパージャ１７が略
等間隔に配設されている。この給水スパージャ１７は第
３図に示すように上部チムニ１４に形成された貫通孔１
８を介して間隙１６に挿入され、その端部は支持金具１
９にて支持されている。この給水スパージャ１７のノズ
ル２０は下方に向けて取り付けられている。よって、上
述した第１実施例と同様の効果を得ることができる。さ
らには自然循環流がジェットポンプ効果によって促進さ
れ、ダウンカマ１５の冷却材が上・下部チムニ１３．１
４内へ間隙１６を介して流入するのを防止させることが
できる。In FIG. 2, water supply spargers 17 are arranged at approximately equal intervals in an annular gap 16 formed between the upper chimney 14 and the lower chimney 13. This water supply sparger 17 is connected to a through hole 1 formed in the upper chimney 14 as shown in FIG.
8 into the gap 16, and its end is connected to the support fitting 1.
Supported by 9. The nozzle 20 of this water supply sparger 17 is attached facing downward. Therefore, the same effects as in the first embodiment described above can be obtained. Furthermore, the natural circulation flow is promoted by the jet pump effect, and the coolant in the downcomer 15 is transferred to the upper and lower chimneys 13.1.
4 through the gap 16.
本発明の一実施例に係る沸騰水型原子炉によれば１通常
運転時の自然循環流路の他に過渡時の原子炉水位が低下
した場合における自然循環流路を確保したので、通常運
転時の水位を下げることができ、それにともなって原子
炉圧力容器の高さを低くすることができる。According to the boiling water reactor according to one embodiment of the present invention, in addition to the natural circulation channel during normal operation, a natural circulation channel is provided for use when the reactor water level drops during a transient period. It is possible to lower the water level at the time of the reactor, and accordingly, the height of the reactor pressure vessel can be lowered.
第１図及び第２図は本発明の第１実施例及び第２実施例
を示す沸騰水型原子炉の縦断面図、第３図は第２図のＥ
部拡大図、第４図は沸騰水型原子炉の従来例を示す縦断
面図である。
１・・・原子炉圧力容器 ３・・・炉心１１・・・蒸気
乾燥器 １２．１７・・・給水スパージャ１３・・
・下部チムニ
１４・・・」二部チムニ1 and 2 are vertical cross-sectional views of boiling water reactors showing the first and second embodiments of the present invention, and FIG. 3 is the E of FIG.
FIG. 4 is a vertical sectional view showing a conventional example of a boiling water reactor. 1...Reactor pressure vessel 3...Reactor core 11...Steam dryer 12.17...Water supply sparger 13...
・Lower chimney 14..." Second part chimney
Claims (1)
成る下部チムニと、この下部チムニ内に収容された炉心
と、この下部チムニの上端を囲繞し上端開口部を運転水
位より下方に形成した上部チムニと、この上部チムニの
上方に配設された蒸気乾燥器と、前記下部チムニの上端
より下方に開口を配設した給水スパージャとから成るこ
とを特徴とする沸騰水型原子炉。A lower chimney arranged in a reactor pressure vessel and having an opening formed above, a reactor core housed in this lower chimney, and a structure surrounding the upper end of this lower chimney so that the upper end opening is located below the operating water level. A boiling water nuclear reactor comprising: a formed upper chimney; a steam dryer disposed above the upper chimney; and a water supply sparger having an opening below the upper end of the lower chimney.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63209420A JPH0259697A (en) | 1988-08-25 | 1988-08-25 | Boiling water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63209420A JPH0259697A (en) | 1988-08-25 | 1988-08-25 | Boiling water reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0259697A true JPH0259697A (en) | 1990-02-28 |
Family
ID=16572577
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63209420A Pending JPH0259697A (en) | 1988-08-25 | 1988-08-25 | Boiling water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0259697A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007033074A (en) * | 2005-07-22 | 2007-02-08 | Toshiba Corp | Nuclear reactor water supply device and water supply method |
| WO2007018286A1 (en) * | 2005-08-11 | 2007-02-15 | Kabushiki Kaisha Toshiba | Natural circulation type boiling water reactor |
| WO2016022445A1 (en) * | 2014-08-06 | 2016-02-11 | Ge-Hitachi Nuclear Energy Americas Llc | Chimney assembly of a reactor pressure vessel and method of storing the same during a nuclear reactor outage |
-
1988
- 1988-08-25 JP JP63209420A patent/JPH0259697A/en active Pending
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007033074A (en) * | 2005-07-22 | 2007-02-08 | Toshiba Corp | Nuclear reactor water supply device and water supply method |
| JP4709602B2 (en) * | 2005-07-22 | 2011-06-22 | 株式会社東芝 | Reactor water supply equipment |
| WO2007018286A1 (en) * | 2005-08-11 | 2007-02-15 | Kabushiki Kaisha Toshiba | Natural circulation type boiling water reactor |
| US8675808B2 (en) | 2005-08-11 | 2014-03-18 | Kabushiki Kaisha Toshiba | Natural circulation type boiling water reactor |
| WO2016022445A1 (en) * | 2014-08-06 | 2016-02-11 | Ge-Hitachi Nuclear Energy Americas Llc | Chimney assembly of a reactor pressure vessel and method of storing the same during a nuclear reactor outage |
| US9721687B2 (en) | 2014-08-06 | 2017-08-01 | Ge-Hitachi Nuclear Energy Americas Llc | Method of storing a chimney assembly of a reactor pressure vessel during a nuclear reactor outage |
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