JPH01199192A - Protection of containment vessel - Google Patents
Protection of containment vesselInfo
- Publication number
- JPH01199192A JPH01199192A JP63022702A JP2270288A JPH01199192A JP H01199192 A JPH01199192 A JP H01199192A JP 63022702 A JP63022702 A JP 63022702A JP 2270288 A JP2270288 A JP 2270288A JP H01199192 A JPH01199192 A JP H01199192A
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- gas
- vessel
- dry well
- discharged
- 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
- 239000007788 liquid Substances 0.000 claims abstract description 22
- 230000004992 fission Effects 0.000 claims abstract description 9
- 238000001816 cooling Methods 0.000 claims description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 8
- 239000012530 fluid Substances 0.000 claims description 2
- 239000000126 substance Substances 0.000 claims 1
- 230000001629 suppression Effects 0.000 abstract description 13
- 239000000446 fuel Substances 0.000 abstract description 7
- 238000013022 venting Methods 0.000 abstract description 5
- 239000007789 gas Substances 0.000 abstract 3
- 239000007792 gaseous phase Substances 0.000 abstract 1
- 230000002459 sustained effect Effects 0.000 abstract 1
- 230000000694 effects Effects 0.000 description 7
- 239000000155 melt Substances 0.000 description 3
- 238000013461 design Methods 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000005201 scrubbing Methods 0.000 description 2
- 239000000443 aerosol Substances 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 230000014759 maintenance of location Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 238000011160 research Methods 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、原子力発電プラントにおいて原子炉を格納す
る格納容器の圧力がその設計圧を超えるような原子炉事
故時に、格納容器の破損を防止し、さらに格納容器外へ
の核分裂生成物の放出量を制限する格納容器の保護装置
に関する。Detailed Description of the Invention [Objective of the Invention] (Industrial Field of Application) The present invention provides a method for preventing containment in a nuclear power plant in the event of a nuclear accident in which the pressure in the containment vessel housing the reactor exceeds its design pressure. The present invention relates to a containment vessel protection device that prevents damage to the vessel and limits the amount of fission products released outside the containment vessel.
(従来の技術)
原子力発電プラントにおいては、各種の安全装置が多重
に設置され、どのような事故が発生しても原子炉の健全
性が確保できるように設計されている。安全装置が多重
に故障する可能性は非常に小さいが、各種の安全装置が
多重故障した場合には、原子炉の健全性が喪失し原子炉
の燃料中に保持されていた核分裂生成物(以下FPと略
す)が、原子炉から格納容器に放出される可能性がある
。(Prior Art) In nuclear power plants, various safety devices are installed in multiple layers and are designed to ensure the integrity of the reactor no matter what kind of accident occurs. Although the possibility of multiple failures of safety devices is extremely small, if multiple failures of various safety devices occur, the integrity of the reactor will be lost and the fission products (hereinafter referred to as FP) may be released from the reactor into the containment vessel.
格納容器はこの様な事故が発生してもFPが直接原子力
発電所外へ放出される事がないようにFPをその内部に
閉じこめるために設置されているものである。従って、
FPが格納容器に閉じこめられている間に事故を終息さ
せる事によって例え原子炉の燃料が溶ける様な事故が発
生しても原子力発電所外部へのFP放出を防止すること
ができる。The containment vessel is installed to confine the FP inside the nuclear power plant so that it will not be directly released outside the nuclear power plant even if such an accident occurs. Therefore,
By terminating the accident while the FP is confined in the containment vessel, it is possible to prevent the FP from being released outside the nuclear power plant even if an accident occurs in which the reactor fuel melts.
しかしながら、事故の終息ができない可能性を完全に否
定することはできず、この場合には格納容器内部に閉じ
こめられたFPの崩壊熱によって格納容器内の圧力およ
び温度は徐々に上昇し、格納容器の設計圧力または温度
以上となり、やがては格納容器が破損し、それまで閉じ
こめられた大量のFPが一度に外部へ放出され、発電所
周辺に大きな影響を与える可能性がある。However, the possibility that the accident cannot be brought to a close cannot be completely ruled out, and in this case, the pressure and temperature inside the containment vessel will gradually rise due to the decay heat of the FP trapped inside the containment vessel, and the pressure and temperature inside the containment vessel will gradually increase. If the pressure or temperature exceeds the design pressure or temperature of the power plant, the containment vessel will eventually break, and a large amount of FP that was previously trapped will be released to the outside at once, potentially having a major impact on the surrounding area of the power plant.
原子炉の燃料が溶融するような事故時の物理挙動および
FP挙動解析によれば、この様な事故時には格納容器を
ベントし、格納容器の破損を防止することによって外部
に放出されるFP量を低減できることがわかっている。According to an analysis of the physical behavior and FP behavior during an accident in which reactor fuel melts, it is possible to vent the containment vessel and prevent damage to the containment vessel in the event of such an accident, thereby reducing the amount of FP released to the outside. It is known that it can be reduced.
(発明が解決しようとする課題)
このため、従来より格納容器の破損を防止するため格納
容器をベントしFP放出量を低減する手段・装置が研究
されている1代表的なものは格納容器からの排気を直接
FP除去装置を通して環境へ放出するものである。FP
除去装置としては、フィルター効果を使用したもの、水
によるスクラビング効果を利用したものなどがある。し
かしながら格納容器からの排気は高圧かつ高温であり、
多量の水蒸気を含んでいるため、FP除去装置が大規模
となりまたFP除去効率をあまり高くできないという問
題点があった。(Problem to be solved by the invention) For this reason, research has been conducted on means and devices for venting the containment vessel and reducing the amount of FP released in order to prevent damage to the containment vessel. The exhaust gas is directly released into the environment through the FP removal device. F.P.
Examples of removal devices include those that use a filter effect and those that utilize a scrubbing effect with water. However, the exhaust gas from the containment vessel is high pressure and high temperature.
Since it contains a large amount of water vapor, there is a problem that the FP removal device has to be large-scale and the FP removal efficiency cannot be very high.
本発明は上記事情に鑑みてなされたもので、その目的は
、JJK子炉の健全性が損なわれさらに格納容器の健全
性も脅かされるような非常に発生確率は低いが原子力発
電所周辺の環境に大きな影響を与える可能性のある事故
において、格納容器の破損を防止し、格納容器外へのF
P放出量を低く抑え住民への影響を低減する格納容器保
護装置を提供することにある。The present invention has been made in view of the above circumstances, and its purpose is to improve the environment around the nuclear power plant, which has a very low probability of occurring, which impairs the integrity of the JJK nuclear reactor and further threatens the integrity of the containment vessel. In the event of an accident that could have a major impact on the
The object of the present invention is to provide a containment vessel protection device that suppresses the amount of P released and reduces the impact on residents.
(課題を解決するための手段)
本発明は上記目的を達成するために、原子炉を格納する
格納容器を有する原子力発電プラントにおいて、格納容
器に一端を開口するベント管と、前記ベント管に接続し
当該ベント管を通る排気を冷却し排気中の水蒸気を凝縮
する冷却槽と、前記冷却槽によって冷却された気液混合
流体の気体と液体を分離する気液分離器と、前記気液分
離器で分離された気体中の核分裂生成物を除去しスタッ
クに排気する核分裂生成物除去装置と、前記気液分離器
で分離された液体を前記格納容器内に戻すドレン管から
構成されたことを特徴とするものである。(Means for Solving the Problems) In order to achieve the above object, the present invention provides a nuclear power plant having a containment vessel for storing a nuclear reactor. a cooling tank that cools the exhaust gas passing through the vent pipe and condenses water vapor in the exhaust gas; a gas-liquid separator that separates gas and liquid from the gas-liquid mixed fluid cooled by the cooling tank; and the gas-liquid separator. A fission product removal device removes fission products from the gas separated by the gas and exhausts the gas into a stack, and a drain pipe returns the liquid separated by the gas-liquid separator to the storage vessel. That is.
(作用)
本発明によれば、格納容器ベント時の高圧・高温の排気
がFP除去装置を通る以前に冷却され、さらに気体と凝
縮した湿分を分離する事によってFP除去装置によるF
P除去効率を高くするとともに必要となるFP除去装置
の容量を低減できる。(Function) According to the present invention, the high-pressure and high-temperature exhaust gas at the time of venting the containment vessel is cooled before passing through the FP removal device, and gas and condensed moisture are further separated.
It is possible to increase the P removal efficiency and reduce the required capacity of the FP removal device.
(実施例) 本発明の実施例を図面を参照して説明する。(Example) Embodiments of the present invention will be described with reference to the drawings.
図において、原子炉圧力容器1を格納する格納容器2は
ドライウェル3とサプレッションプール5を内蔵する圧
力抑制室4からなる。原子炉圧力容器1内の燃料が溶け
る様な事故が発生すると燃料に保持されていたFPは、
S/R弁6を通してサプレッションプール5へ放出され
るか、または原子炉圧力容器1が破損している時にはそ
の破損ロアからドライウェル3へ放出される。また、さ
らに事故が進展すると、溶融した燃料は原子炉圧力容器
1を溶かしドライウェル3へ流出し直接FPをドライウ
ェル3へ放出する。ドライウェル3に放出されたFPは
ドライウェル3からベント管8を通してサプレッション
プール5へ放出される。In the figure, a containment vessel 2 housing a reactor pressure vessel 1 is comprised of a pressure suppression chamber 4 containing a dry well 3 and a suppression pool 5. If an accident occurs in which the fuel in the reactor pressure vessel 1 melts, the FP held in the fuel will
It is released into the suppression pool 5 through the S/R valve 6, or into the dry well 3 from its damaged lower when the reactor pressure vessel 1 is damaged. If the accident progresses further, the molten fuel will melt the reactor pressure vessel 1 and flow into the dry well 3, directly releasing FP into the dry well 3. The FP released into the dry well 3 is released from the dry well 3 into the suppression pool 5 through the vent pipe 8.
S/R弁6またはベント管8からサプレッションプール
へ放出されたエアロゾル状または水溶性のFPはサプレ
ッションプール5の水中においてスクラビングを受け、
圧力抑制室4の気相部に放出されるのはその一部である
。Aerosol or water-soluble FP released from the S/R valve 6 or vent pipe 8 into the suppression pool is scrubbed in the water of the suppression pool 5,
A portion of it is released into the gas phase of the pressure suppression chamber 4.
この様な状態において、原子炉圧力容器1内またはドラ
イウェル3に流出した溶融燃料を冷却し崩壊熱を格納容
器2外に除去できないと、格納容器2内部の圧力および
温度は上昇を続けそのまま放置すると格納容器2が破損
する事となる。この様な場合に圧力抑制室4の気相部に
開口部を持つベント管9に設置されたベント弁10を開
口し、格納容器2をベントすることによって格納容器2
の圧力上昇を抑えその破損を防止する。格納容器2から
の排気はベント管9によって冷却槽11に導かれ、冷却
されるとともに排気中の水蒸気の凝縮を行う。冷却槽1
1から出た気体と液体の混合排気は配管12を通して気
液分離器13に導かれ気体と液体に分離される。分離さ
れた気体は配管14を通して、FP除去用フィルター1
5に6かれFP除去後、配管16を通して原子力発電所
に既設のスタック17を通して環境へ放出される。一方
、気液分離器13を分離された液体はドレン管18を通
して格納容器2のサプレッションプール5に戻される。In such a situation, if the molten fuel that has leaked into the reactor pressure vessel 1 or the dry well 3 cannot be cooled and the decay heat removed from the containment vessel 2, the pressure and temperature inside the containment vessel 2 will continue to rise and the temperature will continue to rise. Then, the containment vessel 2 will be damaged. In such a case, the containment vessel 2 is removed by opening the vent valve 10 installed in the vent pipe 9 having an opening in the gas phase portion of the pressure suppression chamber 4 and venting the containment vessel 2.
Suppress pressure rise and prevent damage. Exhaust gas from the containment vessel 2 is led to a cooling tank 11 by a vent pipe 9, where it is cooled and water vapor in the exhaust gas is condensed. Cooling tank 1
The mixed gas and liquid exhaust gas discharged from the pipe 12 is led to the gas-liquid separator 13 and separated into gas and liquid. The separated gas passes through the pipe 14 to the FP removal filter 1
After removing the FP from 5 and 6, it is discharged into the environment through a stack 17 already installed at the nuclear power plant through a pipe 16. On the other hand, the liquid separated by the gas-liquid separator 13 is returned to the suppression pool 5 of the storage vessel 2 through the drain pipe 18.
以上説明したように、本発明によれば格納容器ベント時
の高圧・高温の排気がFP除去装置を通る以前に冷却さ
れ、さらに気体と凝縮した湿分を分離する事によってF
P除去装置によるFP除去効率を高くするとともに必要
となるFP除去装置の容量の低減を可能としている。ま
た、冷却時の水蒸気凝縮時の拡散泳動によるFP除去効
果および気液分離装置におけるスクラビング効果による
FP除去によってさらにFPの除去が可能となっている
。しかも凝縮水を格納容器に戻すことによってFPの保
持効果を高めているので、外部へのFP放出量が非常に
少ない格納容器ベント操作が可能となるというすぐれた
効果を奏する。As explained above, according to the present invention, the high-pressure and high-temperature exhaust gas at the time of venting the containment vessel is cooled before passing through the FP removal device, and the gas and condensed moisture are further separated.
This makes it possible to increase the FP removal efficiency of the P removal device and to reduce the required capacity of the FP removal device. Further, FP can be further removed by the FP removal effect due to diffusion migration during water vapor condensation during cooling and the FP removal due to the scrubbing effect in the gas-liquid separator. Moreover, since the FP retention effect is enhanced by returning the condensed water to the containment vessel, an excellent effect is achieved in that it becomes possible to perform a containment vessel vent operation with a very small amount of FP released to the outside.
図は本発明の一実施例の概略構成図である。
1・・・原子炉圧力容器 2・・・格納容器3・・・ド
ライウェル 4・・・圧力抑制室5・・・サプレッシ
ョンプール 6・・・S/R弁7・・・破断口
8,9・・・ベント管lO・・・ベント弁
11・・・冷却槽12、14.16・・・配管 13
・・・気液分離器15・・・FP除去装置(フィルタ)The figure is a schematic configuration diagram of an embodiment of the present invention. 1...Reactor pressure vessel 2...Containment vessel 3...Dry well 4...Pressure suppression chamber 5...Suppression pool 6...S/R valve 7...Break port
8, 9...Vent pipe lO...Vent valve
11...Cooling tank 12, 14.16...Piping 13
... Gas-liquid separator 15 ... FP removal device (filter)
Claims (1)
トにおいて、前記格納容器に一端を開口するベント管と
、前記ベント管に接続し当該ベント管を通る排気を冷却
し排気中の水蒸気を凝縮する冷却槽と、前記冷却槽によ
って冷却された気液混合流体の気体と液体を分離する気
液分離器と、前記気液分離器で分離された気体中の核分
裂生成物を除去しスタックに排気する核分裂生成物除去
装置と、前記気液分離器で分離された液体を前記格納容
器内に戻すドレン管から構成されたことを特徴とする格
納容器保護装置。In a nuclear power plant having a containment vessel for storing a nuclear reactor, a vent pipe having one end opened in the containment vessel, and a cooling tank connected to the vent pipe to cool exhaust gas passing through the vent pipe and condense water vapor in the exhaust gas. a gas-liquid separator that separates gas and liquid from the gas-liquid mixed fluid cooled by the cooling tank; and a fission generator that removes fission products from the gas separated by the gas-liquid separator and exhausts them into the stack. A containment vessel protection device comprising: a substance removal device; and a drain pipe for returning the liquid separated by the gas-liquid separator into the containment vessel.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63022702A JPH01199192A (en) | 1988-02-04 | 1988-02-04 | Protection of containment vessel |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63022702A JPH01199192A (en) | 1988-02-04 | 1988-02-04 | Protection of containment vessel |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH01199192A true JPH01199192A (en) | 1989-08-10 |
Family
ID=12090193
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP63022702A Pending JPH01199192A (en) | 1988-02-04 | 1988-02-04 | Protection of containment vessel |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH01199192A (en) |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6069930A (en) * | 1997-06-27 | 2000-05-30 | General Electric Company | Modified passive containment cooling system for a nuclear reactor |
WO2001017569A2 (en) | 1999-09-03 | 2001-03-15 | Amersham Plc | Improved container composition for radiopharmaceutical agents |
JP2013072879A (en) * | 2011-09-28 | 2013-04-22 | Westinghouse Electric Germany Gmbh | Condensation chamber cooling system |
JP2013185828A (en) * | 2012-03-05 | 2013-09-19 | Mitsubishi Heavy Ind Ltd | Containment vessel maintenance equipment and method for containment vessel maintenance |
JP2015004671A (en) * | 2013-06-19 | 2015-01-08 | コリア アトミック エナジー リサーチ インスティチュート | Reactor containment structure cooling system |
JP2020098166A (en) * | 2018-12-19 | 2020-06-25 | 日立Geニュークリア・エナジー株式会社 | Emergency gas processing equipment and emergency gas processing method |
-
1988
- 1988-02-04 JP JP63022702A patent/JPH01199192A/en active Pending
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US6069930A (en) * | 1997-06-27 | 2000-05-30 | General Electric Company | Modified passive containment cooling system for a nuclear reactor |
WO2001017569A2 (en) | 1999-09-03 | 2001-03-15 | Amersham Plc | Improved container composition for radiopharmaceutical agents |
JP2013072879A (en) * | 2011-09-28 | 2013-04-22 | Westinghouse Electric Germany Gmbh | Condensation chamber cooling system |
JP2013185828A (en) * | 2012-03-05 | 2013-09-19 | Mitsubishi Heavy Ind Ltd | Containment vessel maintenance equipment and method for containment vessel maintenance |
JP2015004671A (en) * | 2013-06-19 | 2015-01-08 | コリア アトミック エナジー リサーチ インスティチュート | Reactor containment structure cooling system |
US9984778B2 (en) | 2013-06-19 | 2018-05-29 | Korea Atomic Energy Research Institute | Cooling system of nuclear reactor containment structure |
JP2020098166A (en) * | 2018-12-19 | 2020-06-25 | 日立Geニュークリア・エナジー株式会社 | Emergency gas processing equipment and emergency gas processing method |
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