JPS61191995A - Containment facility for nuclear reactor - Google Patents

Containment facility for nuclear reactor

Info

Publication number
JPS61191995A
JPS61191995A JP60031455A JP3145585A JPS61191995A JP S61191995 A JPS61191995 A JP S61191995A JP 60031455 A JP60031455 A JP 60031455A JP 3145585 A JP3145585 A JP 3145585A JP S61191995 A JPS61191995 A JP S61191995A
Authority
JP
Japan
Prior art keywords
reactor
reactor containment
pool
gas
containment vessel
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
Application number
JP60031455A
Other languages
Japanese (ja)
Inventor
児玉 資
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Atomic Industry Group Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Toshiba Corp, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP60031455A priority Critical patent/JPS61191995A/en
Publication of JPS61191995A publication Critical patent/JPS61191995A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は、原子炉格納施設、特に事故時に原子炉を外部
から隔離するとともに外部環境への放射能の放出を制限
する原子炉格納施設に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a nuclear reactor containment facility, and particularly to a nuclear reactor containment facility that isolates a nuclear reactor from the outside in the event of an accident and limits the release of radioactivity to the outside environment.

〔発明の技術的背景とその問題点〕[Technical background of the invention and its problems]

例えば発電用沸騰水型原子炉においては、通常、原子炉
格納施設は原子炉を内蔵する原子炉格納容器と、この原
子炉格納容器を収納する原子炉棟と。
For example, in a boiling water reactor for power generation, the reactor containment facility usually consists of a reactor containment vessel that houses the reactor, and a reactor building that houses this reactor containment vessel.

さらに゛この原子炉棟内の空気を処理する非常用ガス処
理設備とを備えているので、原子炉事故時には原子炉を
原子炉格納容器と原子炉棟によって外部に対して二重に
隔離しており、また、原子炉格納容器から原子炉棟内へ
漏洩してくる微量の放射能は非常用ガス処理設備により
処理して外部環境への放射能の放出を制限するように構
成されている。そして、非常用ガス処理設備は、上記し
たような機能を効果的に行なうために比較的温度の低い
気体を処理するように設計されており、温度の高い気体
を処理するようには構成されていない。
Furthermore, it is equipped with emergency gas treatment equipment to treat the air inside this reactor building, so in the event of a reactor accident, the reactor can be doubly isolated from the outside by the reactor containment vessel and the reactor building. Furthermore, the structure is such that any minute amount of radioactivity leaking from the reactor containment vessel into the reactor building is treated by emergency gas processing equipment to limit the release of radioactivity to the outside environment. In order to effectively perform the functions described above, emergency gas processing equipment is designed to process relatively low-temperature gas, and is not configured to process high-temperature gas. do not have.

ところで、予期しない事態例えば原子炉格納容器内へ大
量の気体が注入されるような事態あるいは冷却材漏洩事
故時において格納容器スプレィ系が不作動となるような
事態あるいは原子炉格納容器内に大量の水素ガスが発生
するような事態が生起した場合を想定すると、原子炉格
納容器内の圧力上昇を抑制する必要上または原子炉格納
容器内の空気を置換する必要上、原子炉格納容器内の空
気を外部に放出することが生じることになる。
By the way, unexpected situations such as a situation in which a large amount of gas is injected into the reactor containment vessel, a situation in which the containment vessel spray system becomes inoperable in the event of a coolant leak accident, or a situation in which a large amount of gas is injected into the reactor containment vessel, Assuming that a situation occurs in which hydrogen gas is generated, the air inside the reactor containment vessel must be will be released to the outside.

一方、このような不測事態が生起した場合、yK子炉格
納容器は圧力上昇に伴い自動的に隔離されるように構成
されているので、原子炉格納容器内の気体を冷却するた
めの冷却装置もその機能を停止することになる。その結
果、原子炉格納容器内の気体は原子炉からの放熱により
暖められ、温度が上昇することになるので、このような
温度の高い気体は非常用ガス処理設備により処理して外
部に放出することができない。そこで、このような場合
原子炉格納容器内の気体を放出する方法としてパージ用
ファンへ至る経路を用いて放出することが考えられるが
、この方法は、上記したような不測事態において原子炉
を外部から隔離するための原子炉格納容器の機能を保護
することになり、総合的にみると外部環境への放射能の
放出は最少限に抑制できるということが云えるが、矢張
り外部環境へ放射能が放出されることになり、非常用ガ
ス処理設備を用いて放出するように十分な放射能除去効
果は期待できない。
On the other hand, if such an unexpected situation occurs, the yK reactor containment vessel is configured to be automatically isolated as the pressure increases, so the cooling system for cooling the gas inside the reactor containment vessel is will also cease to function. As a result, the gas inside the reactor containment vessel will be warmed by heat radiation from the reactor, and its temperature will rise, so such high-temperature gas must be treated by emergency gas processing equipment and released to the outside. I can't. Therefore, in such a case, one possible way to release the gas in the reactor containment vessel is to use a path leading to the purge fan, but this method does not allow the reactor to be removed from the outside in the event of an unexpected situation such as the one described above. Overall, it can be said that the release of radioactivity into the external environment can be suppressed to a minimum. Therefore, a sufficient effect of removing radioactivity cannot be expected compared to releasing it using emergency gas processing equipment.

〔発明の目的J 本発明は、上記事情に鑑みてなされたもので、その目的
は、原子炉格納容器内の気体の温度が高い状態で上記し
たような不測事態が生起しても外部環境へ放射能を放出
することがないようにした原子炉格納施設を提供するこ
とにある。
[Purpose of the Invention J The present invention was made in view of the above circumstances, and its purpose is to prevent the gas from leaking to the external environment even if the above-mentioned unexpected situation occurs when the temperature of the gas in the reactor containment vessel is high. The objective is to provide a nuclear reactor containment facility that does not release radioactivity.

〔発明の概要〕[Summary of the invention]

本発明は、上記目的を達成するために、原子炉を内蔵す
る原子炉格納容器と、この原子炉格納容器を収納する原
子炉棟と、この原子炉棟内の気体を処理する非常用ガス
処理設備とを備えた原子炉格納施設において、前記原子
炉棟内にプールを設置すると共にこのプールと前記原子
炉格納容器とを接続する放出配管系を配設して前記原子
炉路°納容器内の気体を前記放出配管系を経て前記プー
ル水中に放出することができるようにしたものである。
In order to achieve the above object, the present invention provides a reactor containment vessel that houses a nuclear reactor, a reactor building that houses this reactor containment vessel, and an emergency gas treatment system that processes gas in this reactor building. In a reactor containment facility equipped with equipment, a pool is installed in the reactor building, and a release piping system is installed to connect the pool and the reactor containment vessel, and The gas can be discharged into the pool water through the discharge piping system.

〔発明の実施例〕[Embodiments of the invention]

本発明の実施例を図面を参照して説明する。 Embodiments of the present invention will be described with reference to the drawings.

図は本発明の一実施例の概略配置図を示したものである
。同図に示すように、原子炉1を内蔵した原子炉格納容
器2は、原子炉棟3内の所定個所に設置されている。こ
の原子炉棟3内の気体を処理するための後記する非常用
ガス処理設備4が設けられている。この非常用ガス処理
設備4は原子炉棟3外に設けた非常用ガス処理装置7と
、原子炉棟3からの吸入配管系8および原子炉格納容器
2からの吸込配管系9と、この吸込配管系9と前記吸込
配管8とを接続する配管系lOとから構成されている。
The figure shows a schematic layout of an embodiment of the present invention. As shown in the figure, a reactor containment vessel 2 containing a nuclear reactor 1 is installed at a predetermined location within a reactor building 3. Emergency gas treatment equipment 4, which will be described later, is provided to treat the gas within this reactor building 3. This emergency gas processing equipment 4 includes an emergency gas processing equipment 7 installed outside the reactor building 3, a suction piping system 8 from the reactor building 3, a suction piping system 9 from the reactor containment vessel 2, and a suction piping system 9 from the reactor containment vessel 2. It is composed of a piping system 9 and a piping system lO connecting the suction piping 8.

また、原子炉格納容器2内の気体は、吸込配管系9とこ
の配管系9より分岐する配管系11を経由してパージ用
ファン6により放出できるように構成されている。さら
に吸込配管系9より分岐して原子炉棟3内に配置された
プール5内へ接続される放出配管系12を設け、この配
管系12のプール水中内には放出口13を設けている。
Further, the gas in the reactor containment vessel 2 is configured to be discharged by a purge fan 6 via a suction piping system 9 and a piping system 11 branching from this piping system 9. Furthermore, a discharge piping system 12 is provided which branches from the suction piping system 9 and is connected to the pool 5 disposed within the reactor building 3, and a discharge port 13 is provided in the pool water of this piping system 12.

上記したように構成された本実施例の原子炉格納施設に
おいて、例えば原子炉格納容器2内の気体の温度が高い
状態下にあり、この条件下でさらに既に説明したような
不測事態が生起すると原子炉格納容器2内の高温の気体
は吸込配管系9および放出配管系12を経由して放出口
13よりプール水中へ放出されるので、放出された気体
はプール水により冷却された後、原子炉棟3内に放出さ
れる。
In the reactor containment facility of this embodiment configured as described above, for example, if the temperature of the gas in the reactor containment vessel 2 is high, and under this condition an unexpected situation as already described occurs. The high-temperature gas in the reactor containment vessel 2 is released into the pool water from the outlet 13 via the suction piping system 9 and the discharge piping system 12, so the released gas is cooled by the pool water and then becomes atomic. It is released into the furnace building 3.

その後は吸込配管系8を経由して非常用ガス処理装置7
へ吸入され、気体中の放射能が除去された後、外部環境
中へ放出するものである。
After that, the emergency gas treatment device 7 is passed through the suction piping system 8.
After the radioactivity in the gas is removed, it is released into the external environment.

しかして、プール水中における気液接触時に溶解性の放
射性物質等はプール水中へ吸収除去されるため外部環境
中への放射能放出のより一層の抑制に寄与することがで
きる。しかも、溶解性放射性物質の溶解度を高める必要
があれば、沃化メチル溶液等をプール水として用いるこ
ともできる。
Therefore, soluble radioactive substances and the like are absorbed and removed into the pool water during gas-liquid contact in the pool water, which can contribute to further suppressing the release of radioactivity into the external environment. Moreover, if it is necessary to increase the solubility of the soluble radioactive substance, a methyl iodide solution or the like can be used as the pool water.

ところで、上記実施例では、プール5に至る放出配管系
12としては従来より設置されている吸込配管系9より
分岐した場合について説明しているが、原子炉格納容器
2とプール5との配置関係によっては両者を直接に接続
する配管系を設置してもよいことは勿論であり、要は原
子炉格納容器内の気体を必要によりプール水中に放出す
ることのできる構成とすればよい。また、プールとして
は原子炉棟内に設置されている燃料貯蔵プールまたは機
器仮置ピット等を用いてもよく新たに設置してもよい。
Incidentally, in the above embodiment, a case has been described in which the discharge piping system 12 leading to the pool 5 is branched from the conventionally installed suction piping system 9, but the arrangement relationship between the reactor containment vessel 2 and the pool 5 is Depending on the situation, it is of course possible to install a piping system that directly connects the two, but the point is that the structure may be such that the gas in the reactor containment vessel can be discharged into the pool water if necessary. Further, the pool may be a fuel storage pool or a temporary equipment storage pit installed in the reactor building, or may be newly installed.

さらに、気体の放出量が大きいとプールの冷却が必要と
なり、このときは既設の燃料貯蔵プール冷却装置を用い
てもよく、また、新たに冷却装置を設けてもよい。
Furthermore, if the amount of gas released is large, the pool needs to be cooled, and in this case, an existing fuel storage pool cooling device may be used, or a new cooling device may be installed.

〔発明の効果〕〔Effect of the invention〕

以上説明したように、本発明の原子炉格納施設によれば
、原子炉格納容器内の気体の温度が高い状態下で、かつ
この高温の気体を放出するような不測事態が起きてもこ
の高温の気体をプール水中に放出して所定温度まで冷却
した後に、非常用ガス処理設備を経て放出するようにし
ているため外部環境への放射能放出を大幅に低減抑制す
ることができる。
As explained above, according to the reactor containment facility of the present invention, even if the temperature of the gas in the reactor containment vessel is high and an unexpected situation that causes the release of this high temperature gas occurs, the high temperature Since the gas is released into the pool water, cooled to a predetermined temperature, and then released through the emergency gas processing equipment, it is possible to significantly reduce and suppress the release of radioactivity into the external environment.

【図面の簡単な説明】[Brief explanation of drawings]

図は本発明の一実施例の概略配置図である。 1・・・原子炉 2・・・原子炉格納容器 3・・・原子炉棟 4・・・非常用ガス処理設備 5・・・プール 8.9・・・吸込配管系 12・・・放出配管系 The figure is a schematic layout diagram of an embodiment of the present invention. 1... Nuclear reactor 2...Reactor containment vessel 3...Reactor building 4...Emergency gas processing equipment 5...pool 8.9...Suction piping system 12...Discharge piping system

Claims (3)

【特許請求の範囲】[Claims] (1)原子炉を内蔵する原子炉格納容器と、該原子炉格
納容器を収納する原子炉棟と、該原子炉棟内の気体を処
理する非常用ガス処理設備とを備えた原子炉格納施設に
おいて、前記原子炉棟内にプールを設置すると共に該プ
ールと前記原子炉格納容器とを接続する放出配管系を配
設して前記原子炉格納器内の気体を前記放出配管系を経
て前記プール水中に放出できるようにしたことを特徴と
する原子炉格納施設。
(1) Reactor containment facility equipped with a reactor containment vessel that houses a nuclear reactor, a reactor building that houses the reactor containment vessel, and emergency gas processing equipment that processes gas within the reactor building. A pool is installed in the reactor building, and a release piping system is provided to connect the pool and the reactor containment vessel, and the gas in the reactor containment vessel is transferred to the pool through the release piping system. A nuclear reactor containment facility characterized by being able to release water into the water.
(2)前記プールは燃料貯蔵プールまたは機器仮置ピッ
トが用いられる特許請求の範囲第1項記載の原子炉格納
施設。
(2) The reactor containment facility according to claim 1, wherein the pool is a fuel storage pool or a temporary equipment storage pit.
(3)前記プール水は冷却水または沃化メチル溶液が用
いられている特許請求の範囲第1項記載の原子炉格納施
設。
(3) The reactor containment facility according to claim 1, wherein cooling water or methyl iodide solution is used as the pool water.
JP60031455A 1985-02-21 1985-02-21 Containment facility for nuclear reactor Pending JPS61191995A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60031455A JPS61191995A (en) 1985-02-21 1985-02-21 Containment facility for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60031455A JPS61191995A (en) 1985-02-21 1985-02-21 Containment facility for nuclear reactor

Publications (1)

Publication Number Publication Date
JPS61191995A true JPS61191995A (en) 1986-08-26

Family

ID=12331725

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60031455A Pending JPS61191995A (en) 1985-02-21 1985-02-21 Containment facility for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS61191995A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5610025A (en) * 1992-01-31 1997-03-11 Actimed Laboratories, Inc. Inhibition of interfering endogenous enzyme activity in assays of biological fluids
JP2016045116A (en) * 2014-08-25 2016-04-04 日立Geニュークリア・エナジー株式会社 Radioactive substance removal method and radioactive substance removal apparatus
JP2016527499A (en) * 2013-07-19 2016-09-08 アレヴァ ゲゼルシャフト ミット ベシュレンクテル ハフツングAreva GmbH Ventilation system for use in severe accidents in nuclear facilities and method of operation thereof

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5610025A (en) * 1992-01-31 1997-03-11 Actimed Laboratories, Inc. Inhibition of interfering endogenous enzyme activity in assays of biological fluids
JP2016527499A (en) * 2013-07-19 2016-09-08 アレヴァ ゲゼルシャフト ミット ベシュレンクテル ハフツングAreva GmbH Ventilation system for use in severe accidents in nuclear facilities and method of operation thereof
JP2016045116A (en) * 2014-08-25 2016-04-04 日立Geニュークリア・エナジー株式会社 Radioactive substance removal method and radioactive substance removal apparatus

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