JPS643107Y2 - - Google Patents
Info
- Publication number
- JPS643107Y2 JPS643107Y2 JP1982140300U JP14030082U JPS643107Y2 JP S643107 Y2 JPS643107 Y2 JP S643107Y2 JP 1982140300 U JP1982140300 U JP 1982140300U JP 14030082 U JP14030082 U JP 14030082U JP S643107 Y2 JPS643107 Y2 JP S643107Y2
- Authority
- JP
- Japan
- Prior art keywords
- cooling water
- pool
- storage rack
- fuel
- inlet pipe
- 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.)
- Expired
Links
- 239000000498 cooling water Substances 0.000 claims description 26
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 7
- 238000001816 cooling Methods 0.000 claims description 2
- 239000000446 fuel Substances 0.000 description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 15
- 230000000694 effects Effects 0.000 description 7
- 238000002347 injection Methods 0.000 description 4
- 239000007924 injection Substances 0.000 description 4
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 238000009423 ventilation Methods 0.000 description 2
- 230000001771 impaired effect Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- 230000001698 pyrogenic effect Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 230000000630 rising effect 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【考案の詳細な説明】
本考案は、発熱性の放射性物質、特に使用済核
燃料の貯蔵設備に関する。[Detailed Description of the Invention] The present invention relates to a storage facility for pyrogenic radioactive materials, particularly spent nuclear fuel.
原子力発電所における原子炉内の核燃料集合体
は、おおよそ３年間燃焼させたのち、新しい核燃
料集合体と取替えられる。原子炉から取り出され
た核燃料集合体すなわち使用済核燃料は、未だい
く分余熱を持つているので、発電所内に設けられ
た使用済燃料集合体貯蔵設備内にいつたん貯蔵
し、ここで充分に冷却したのち再処理工場に運び
出される。使用済燃料貯蔵設備は、燃料プール、
及びこの中に設けられた燃料貯蔵ラツク、並びに
燃料プールに冷却水を給水するための給水装置な
どから成る。この冷却水は又、人体への放射線障
害を防ぐための水しやへいの役目も持つている。
したがつて、プール内の冷却水はいかなる場合に
おいても所定の水深が確保されなければならな
い。 Nuclear fuel assemblies in nuclear reactors in nuclear power plants are burned for approximately three years and then replaced with new nuclear fuel assemblies. Nuclear fuel assemblies, that is, spent nuclear fuel, taken out from the reactor still have some residual heat, so they are temporarily stored in the spent fuel assembly storage facility installed within the power plant, where they are cooled sufficiently. It is then transported to a reprocessing plant. Spent fuel storage facilities include fuel pools,
It consists of a fuel storage rack installed therein, a water supply device for supplying cooling water to the fuel pool, etc. This cooling water also serves as a water source to prevent radiation damage to the human body.
Therefore, the cooling water in the pool must have a predetermined depth in any case.
従来の燃料プール内の配置の概要を第１図に示
す。図において０１は燃料貯蔵ラツク、０２は冷
却水入口配管、０３は冷却水出口配管を示す。冷
却水は入口配管０２の先端からプール０４に入
り、下降してプールの底に至り、貯蔵ラツク０１
内の使用済核燃料（以下燃料と称す。）を冷却す
ると同時に昇温し、自然対流で上昇して、出口配
管０３からプール外へ出ることになる。冷却水の
注入を止めた場合、サイフオン効果で、プール０
４内の水が入口配管０２を逆流して排出されるお
それがあるが、貯蔵ラツク０１内の燃料は水で遮
蔽されているため、プール０４の水面は常に燃料
が露出しないように保つ必要がある。このため、
従来の設備では冷却水入口管０２は、プール０４
の底部まで配管することができず、その先端を燃
料貯蔵ラツク０１の頂部よりも上方で止めざるを
得なかつた。従つて冷却水は下降の途中で上昇す
る温水と混合して冷たい水が下端まで充分に行き
渡るとは言い切れず、必ずしも最も理想的な冷却
方法であるとは言えなかつた。 FIG. 1 shows an outline of the arrangement within a conventional fuel pool. In the figure, 01 is a fuel storage rack, 02 is a cooling water inlet pipe, and 03 is a cooling water outlet pipe. Cooling water enters the pool 04 from the tip of the inlet pipe 02, descends to the bottom of the pool, and is transferred to the storage rack 01.
The spent nuclear fuel (hereinafter referred to as fuel) inside is cooled and raised in temperature at the same time, rises due to natural convection, and exits from the outlet pipe 03 to the outside of the pool. If the cooling water injection is stopped, the siphon effect will reduce the pool to 0.
There is a risk that the water in the pool 04 will flow back through the inlet pipe 02 and be discharged, but since the fuel in the storage rack 01 is shielded by water, the water surface of the pool 04 must always be kept so that the fuel is not exposed. be. For this reason,
In conventional equipment, the cooling water inlet pipe 02 is connected to the pool 04.
It was not possible to run the piping all the way to the bottom of the fuel storage rack 01, and the tip had to be stopped above the top of the fuel storage rack 01. Therefore, the cooling water mixes with the rising hot water on its way down, and it cannot be said that the cold water sufficiently reaches the bottom end, so it cannot necessarily be said that this is the most ideal cooling method.
本考案は、前述した従来設備の問題点に鑑みな
されたものである。すなわち、本考案は、ラツク
の上方のプール壁に突出した冷却水入口配管を鉛
直下方に延出してラツク下部に開口せしめると共
に、ラツク上方の入口配管鉛直部分に貫通孔を形
成し、サイフオン効果による冷却水逆流排出を防
止しつつ崩壊熱除去の効率向上を達成した貯蔵設
備を提供せんとするものである。 The present invention was devised in view of the problems of the conventional equipment mentioned above. That is, in the present invention, the cooling water inlet pipe protruding from the pool wall above the rack is extended vertically downward to open at the bottom of the rack, and a through hole is formed in the vertical part of the inlet pipe above the rack, so that the cooling water inlet pipe protrudes from the pool wall above the rack. It is an object of the present invention to provide a storage facility that achieves improved efficiency in decay heat removal while preventing backflow of cooling water.
以下、本考案を図示の実施例に基づいて説明す
る。 Hereinafter, the present invention will be explained based on the illustrated embodiments.
第２図において燃料貯蔵ラツク１は、燃料を受
容する矩形断面空間（図示しない）を多数もつて
いる。冷却水入口配管３及び冷却水出口配管５
は、ラツク１の上方のプール壁から突出してい
る。入口配管３の開口に対向した漏斗部９をもつ
冷却水案内管１１は、ほゞ鉛直下方に延びて開口
している。入口配管３と漏斗部９との間には、貫
通空間１３が形成されているが、案内管１１は入
口配管３の一部と考えてもよく、したがつて後述
するように一体的に構成してもよい。 In FIG. 2, the fuel storage rack 1 has a number of rectangular cross-sectional spaces (not shown) for receiving fuel. Cooling water inlet piping 3 and cooling water outlet piping 5
protrudes from the pool wall above rack 1. A cooling water guide pipe 11 having a funnel portion 9 facing the opening of the inlet pipe 3 extends substantially vertically downward and opens. A through space 13 is formed between the inlet pipe 3 and the funnel part 9, but the guide pipe 11 may be considered to be a part of the inlet pipe 3, and therefore is integrally configured as described below. You may.
図示しないポンプによつて吐出された冷却水
は、案内管１１に入り、プール７の底部へ導か
れ、燃料貯蔵ラツク１の下方へ低温の冷却水を送
入する。案内管１１は、プール７の壁及び底から
図示しないサポートにより支持され、その入口の
漏斗部９は冷却水の損失ヘツドを減らす。そし
て、ラツク１の下方に供給された冷却水は十分燃
料を冷却して上昇し、出口配管５から流出する。
燃料貯蔵ラツク１の頂部よりも上に漏斗部９を設
けてあるので、注入を止めた場合でも、サイフオ
ン効果でプール７内の水が入口配管３を逆流して
一時排出されても、燃料が水面から露出すること
はない。 Cooling water discharged by a pump (not shown) enters the guide pipe 11, is guided to the bottom of the pool 7, and sends low-temperature cooling water below the fuel storage rack 1. The guide tube 11 is supported by supports (not shown) from the walls and bottom of the pool 7, and a funnel section 9 at its inlet reduces the loss of cooling water head. The cooling water supplied below the rack 1 sufficiently cools the fuel, rises, and flows out from the outlet pipe 5.
Since the funnel part 9 is provided above the top of the fuel storage rack 1, even if the injection is stopped and the water in the pool 7 flows backward through the inlet piping 3 due to the siphon effect and is temporarily discharged, the fuel remains It is never exposed above the water surface.
前記実施例においては、入口配管３と案内管１
１を別体構造としたが、第３図及第４図のように
これらを一体的に構成してもよい。 In the embodiment, the inlet pipe 3 and the guide pipe 1
1 is constructed as a separate structure, but they may be constructed integrally as shown in FIGS. 3 and 4.
第３図において、プールの壁２１より突出した
冷却水入口配管２３の鉛直方向延長部２５を図示
しないラツクの下方迄のばして開口し、ラツクの
上方に位置した貫通孔すなわち通気孔２７が２段
に形成されている。そして、冷却水の注水の場
合、冷水が通気孔２７から管外へ流出する量を僅
少に止めるためには、孔の径を小さくする必要が
ある。注水を止めた場合、サイフオン効果でプー
ル内の水が入口配管２３を逆流して排出され、ブ
ール内の水面が下つて通気孔２７が空気中に露出
すると、通気孔２７から空気が管内に入り、サイ
フオン効果が利かなくなつて水の排出が止る。通
気孔２７の数を多くする程、サイフオン効果を早
く止めることができる。 In FIG. 3, the vertically extending portion 25 of the cooling water inlet pipe 23 protruding from the pool wall 21 is extended and opened below a rack (not shown), and a through hole, that is, a ventilation hole 27 located above the rack is opened in two stages. is formed. In the case of injecting cooling water, in order to minimize the amount of cold water flowing out of the pipe from the vent hole 27, it is necessary to reduce the diameter of the hole. When the water injection is stopped, the water in the pool flows back through the inlet pipe 23 due to the siphon effect and is discharged, and when the water level in the boule falls and the vent 27 is exposed to the air, air enters the pipe from the vent 27. , the siphon effect no longer works and water stops draining. The greater the number of ventilation holes 27, the sooner the siphon effect can be stopped.
第４図は、第３図の更に一部を改変したもの
で、通気孔１２７が冷却水入口配管１２３の内方
に傾むいている。これにより、更にサイフオン効
果による排出が効果的に防止される。符号１２１
は、プールの壁、同１２５は延長部を示す。 FIG. 4 is a further partial modification of FIG. 3, in which the vent hole 127 is inclined inward of the cooling water inlet pipe 123. This further effectively prevents discharge due to the siphon effect. code 121
125 indicates the wall of the pool, and 125 indicates the extension.
以上説明したように、本考案によれば、冷却水
はラツクの下方に供給されるから、冷却水は燃料
の全長に沿つて流れ、受熱による温度上昇に乱さ
れないので、燃料を十分冷却できると共に、何ら
かの原因で注入を停止した際サイフオン効果によ
る逆流現象が生じても水面低下は貫通孔の位置で
停止するので、放射線遮蔽機能が損なわれること
はない。 As explained above, according to the present invention, since the cooling water is supplied below the rack, the cooling water flows along the entire length of the fuel and is not disturbed by the temperature rise due to heat reception, so the fuel can be sufficiently cooled. Even if a backflow phenomenon occurs due to the siphon effect when injection is stopped for some reason, the water level will stop dropping at the through hole, so the radiation shielding function will not be impaired.
第１図は、従来のものの概念図、第２図は、本
考案の実施例を示す立面図、第３図及び第４図
は、前記実施例の１部を改変した改変実施例の部
分図である。
１……ラツク、３……入口配管、５……出口配
管、７……プール、１１……案内管、２３，１２
３……入口配管、１３……貫通空間。
Fig. 1 is a conceptual diagram of the conventional one, Fig. 2 is an elevational view showing an embodiment of the present invention, and Figs. 3 and 4 are parts of a modified embodiment in which a part of the above embodiment is modified. It is a diagram. 1... Rack, 3... Inlet piping, 5... Outlet piping, 7... Pool, 11... Guide pipe, 23, 12
3... Inlet piping, 13... Penetration space.
Claims (1)
用済核燃料を受容するものにおいて、該貯蔵ラツ
クの上方のプール壁に突出した冷却水入口配管を
該貯蔵ラツクの下部迄延出して開口させ、該貯蔵
ラツクの上方のプール壁の適所に冷却水出口配管
を突出させ、該貯蔵ラツクの上方に位置する該入
口配管の鉛直部管壁に貫通孔を穿設してなること
を特徴とする使用済核燃料の貯蔵設備。 In a device that receives spent nuclear fuel in a storage rack installed underwater in a cooling pool, a cooling water inlet pipe that protrudes from the pool wall above the storage rack is extended to the bottom of the storage rack and opened, and the storage rack is opened. Spent nuclear fuel characterized by having a cooling water outlet pipe protruding from a suitable position on the pool wall above the storage rack, and a through hole being bored in the vertical pipe wall of the inlet pipe located above the storage rack. storage facilities.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1982140300U JPS5942999U (en) | 1982-09-16 | 1982-09-16 | Spent nuclear fuel storage facility |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1982140300U JPS5942999U (en) | 1982-09-16 | 1982-09-16 | Spent nuclear fuel storage facility |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5942999U JPS5942999U (en) | 1984-03-21 |
| JPS643107Y2 true JPS643107Y2 (en) | 1989-01-26 |
Family
ID=30314176
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1982140300U Granted JPS5942999U (en) | 1982-09-16 | 1982-09-16 | Spent nuclear fuel storage facility |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5942999U (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CA2412863C (en) * | 2000-08-16 | 2009-12-22 | Eskom | Nuclear reactor plant |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5431898A (en) * | 1977-08-15 | 1979-03-08 | Hitachi Ltd | Spent fuel storage facility with forced circulation device |
| JPS54152792A (en) * | 1978-05-23 | 1979-12-01 | Toshiba Corp | Fuel pool |
-
1982
- 1982-09-16 JP JP1982140300U patent/JPS5942999U/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5431898A (en) * | 1977-08-15 | 1979-03-08 | Hitachi Ltd | Spent fuel storage facility with forced circulation device |
| JPS54152792A (en) * | 1978-05-23 | 1979-12-01 | Toshiba Corp | Fuel pool |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5942999U (en) | 1984-03-21 |
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