JPS59112295A - Oxygen.hydrogen recombiner - Google Patents

Oxygen.hydrogen recombiner

Info

Publication number
JPS59112295A
JPS59112295A JP57221845A JP22184582A JPS59112295A JP S59112295 A JPS59112295 A JP S59112295A JP 57221845 A JP57221845 A JP 57221845A JP 22184582 A JP22184582 A JP 22184582A JP S59112295 A JPS59112295 A JP S59112295A
Authority
JP
Japan
Prior art keywords
oxygen
hydrogen
exhaust gas
reactor
gas treatment
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
JP57221845A
Other languages
Japanese (ja)
Inventor
佐方 裕治
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP57221845A priority Critical patent/JPS59112295A/en
Publication of JPS59112295A publication Critical patent/JPS59112295A/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
    • 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】 〔発明の利用分野〕 本発明は、主に原子力発電設備に係り、特に、原子炉冷
却材喪失事故時に発生する酸素・水素ガスを処理するの
に好適な酸素・水素再結合装置に関するものである。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention mainly relates to nuclear power generation equipment, and in particular, to an oxygen/hydrogen gas suitable for treating oxygen/hydrogen gas generated during a loss of reactor coolant accident. This invention relates to a recombination device.

〔従来技術〕[Prior art]

従来、原子炉冷却材喪失事故時に水・金属反応水の放射
線分解等により、発生する酸素・水素ガスは可燃性ガス
濃度制御系再結合装置で処理されていたので、次のよう
な欠点を有していた。
Conventionally, oxygen and hydrogen gas generated by radiolysis of water and metal reaction water during a loss of reactor coolant accident was treated with a flammable gas concentration control system recombination device, which had the following drawbacks. Was.

可燃性ガス濃度制御系再結合装置は、原子炉冷却材喪失
事故という極めて稀れな時にのみに使用し、かつ原子炉
の安全設備であるため事故時に確実に作用することが要
求されるため、定期的(約4回/年)に点検及び性能テ
ストが必要である。
The combustible gas concentration control system recombination device is used only in the extremely rare event of a loss of reactor coolant accident, and as it is a safety equipment for a nuclear reactor, it is required to function reliably in the event of an accident. Regular inspections and performance tests are required (approximately 4 times a year).

又 通常時は使用しないため、起動には数時間を要する
という欠点があった。
Another disadvantage is that it takes several hours to start up because it is not used normally.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、再結合装置の定期的な性能テストの削
除及び起動時間を短縮する装置を提供することにある。
SUMMARY OF THE INVENTION An object of the present invention is to provide a device that eliminates periodic performance tests of a recombination device and shortens startup time.

〔発明の概要〕[Summary of the invention]

本発明は、可焼性ガス制御系再結合装置が事故時のみ使
用するだめ定期的な性能テストが必要であり、又起動に
時間を要するのに対し、原子力発電設備内で、同様の再
結合処理を行なう排ガス処理設備再結合装置に着目した
ものである。排ガス処理設備再結合装置は、通常運転時
、常に使用されているため、再結合反応は常に監視され
、性能維持が確認でき、又処理零敗は可焼性ガス制御系
に比べ充分に大きいことから本発明をするに至った2 〔発明の実施例〕 以下、本発明の一実施例のフローシートを第1図に示す
The present invention enables similar recombination devices to be used within nuclear power generation facilities, whereas combustible gas control system recombination devices are used only in the event of an accident, require periodic performance tests, and take time to start up. The focus is on the exhaust gas treatment equipment recombination device that performs the treatment. Since the exhaust gas treatment equipment recombination device is always used during normal operation, the recombination reaction is constantly monitored and performance maintenance can be confirmed, and the treatment failure is sufficiently large compared to the combustible gas control system. 2 [Embodiment of the Invention] A flow sheet of an embodiment of the present invention is shown in FIG. 1 below.

原子炉冷却材喪失事故時、原子炉格納容器2同の酸素・
水素水蒸気を含む気体は、ブロワ4により抽気され、弁
5を通って排ガス処理設備再結合装置に導かれる。
At the time of the reactor coolant loss accident, oxygen and
The gas containing hydrogen water vapor is extracted by the blower 4 and guided to the exhaust gas treatment equipment recombination device through the valve 5.

排ガス処理設備は通常運転時、空気抽出器7により、主
復水器6から酸素・水素・空気を抽気し空気抽出器の駆
動蒸気により水素を希釈して、排ガス予熱器10を経て
排ガス再結合器11に導かれ、ここで、酸素・水素は再
結合して水蒸気となり、排ガス復水器12で水蒸気は冷
却凝縮し、復水となる。排ガス復水器12を出た気体は
水素濃度測定器により水素濃度が低く、水素の燃焼若し
くは爆発の恐れがないことを確認した後、活性炭吸着塔
13によりKr、Xeの放射性希ガスの放射能濃度を減
衰し、排気筒14を経て大気に放出される。
During normal operation, the exhaust gas treatment equipment extracts oxygen, hydrogen, and air from the main condenser 6 using the air extractor 7, dilutes the hydrogen with the driving steam of the air extractor, and recombines the exhaust gas through the exhaust gas preheater 10. Oxygen and hydrogen are introduced into a vessel 11, where the oxygen and hydrogen are recombined to become water vapor, and the water vapor is cooled and condensed in an exhaust gas condenser 12 to become condensed water. After confirming that the gas exiting the exhaust gas condenser 12 has a low hydrogen concentration using a hydrogen concentration measuring device and that there is no risk of hydrogen combustion or explosion, the activated carbon adsorption tower 13 removes the radioactivity of radioactive rare gases such as Kr and Xe. The concentration is attenuated and released into the atmosphere through the exhaust stack 14.

原子炉冷却材喪失事故時は、空気抽出器出口弁8は閉と
なり、弁3,5が開となる。ブロワ4を駆動することに
より、原子炉格納容器内の気体は排ガス処理設備へ導か
れる。排ガス処理設備へ導かれた気体は、排ガス予熱器
10で約130°C〜約150’Cまで加熱された後、
排ガス再結合器11で酸素、水素は再結合される。排ガ
ス復水器で水蒸気を除去された気体は活性炭吸着塔を経
て排気筒より大気に放出される。
In the event of a reactor coolant loss accident, the air extractor outlet valve 8 is closed and the valves 3 and 5 are opened. By driving the blower 4, gas within the reactor containment vessel is guided to the exhaust gas treatment facility. The gas led to the exhaust gas treatment equipment is heated to about 130°C to about 150'C in the exhaust gas preheater 10, and then
Oxygen and hydrogen are recombined in the exhaust gas recombiner 11. The gas from which water vapor has been removed in the exhaust gas condenser passes through an activated carbon adsorption tower and is released into the atmosphere from the exhaust stack.

本実施例によれば、原子炉冷却材喪失時の酸素水素を処
理する可燃性ガス制御系再結合装置が不用となる。又、
排ガス処理設備再結合装置は通常状態において常にその
性能が確認されているので、万一の場合に対しても、性
能維持が確保できる。
According to this embodiment, a combustible gas control system recombination device for processing oxygen and hydrogen when reactor coolant is lost becomes unnecessary. or,
Since the performance of the exhaust gas treatment equipment recombination device is always checked under normal conditions, performance can be maintained even in the unlikely event of an emergency.

更に、排ガス処理設備再結合装置は原子炉冷却材喪失時
まで運転状態にあるため、排ガス予熱器10、排ガス再
結合器11は高温状態となっており、事故時、すぐにブ
ロワ4を起動しても再結合反応が完全にできるため、起
動時間を短縮することができる。
Furthermore, since the exhaust gas treatment equipment recombiner remains in operation until the reactor coolant is lost, the exhaust gas preheater 10 and the exhaust gas recombiner 11 are in a high temperature state, and the blower 4 is activated immediately in the event of an accident. Since the recombination reaction can be completed even when the temperature is low, the start-up time can be shortened.

次に本発明の他の実施列を第2図に示す。Next, another embodiment of the present invention is shown in FIG.

本実施例においては、通常運転時、弁16が開、弁3.
5が閉の状態で、空気抽出器7により主復水器6より抽
気される。原子炉冷却材喪失事故時には弁3.5が開、
弁16が閉となる。又、主蒸気が止まるので、空気抽出
器7の駆動蒸気は主蒸気から所内蒸気に切換えられる。
In this embodiment, during normal operation, valve 16 is open, valve 3.
5 is closed, air is extracted from the main condenser 6 by an air extractor 7. In the event of a loss of reactor coolant accident, valve 3.5 opens.
Valve 16 is closed. Also, since the main steam stops, the driving steam for the air extractor 7 is switched from the main steam to the station steam.

本実施例によればブロワが不用になるとともに駆動部分
がなくなるため信頼性が向上する、〔発明の効果〕 本発明によれば、万一の原子炉冷却材喪失事故時に対し
て、再結合器の性能を常時確認することができる。又、
事故時の起動に要する時間を短縮することができる。
According to this embodiment, reliability is improved because the blower is not required and there is no driving part. [Effects of the Invention] According to the present invention, in the event of an accident in which loss of reactor coolant occurs, the recombiner performance can be checked at any time. or,
The time required for startup in the event of an accident can be shortened.

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

第1図は本発明の一実施例のフローシート、第2図は他
の実施例のフローシートである。 1・・・原子炉圧力容器、2・・・原子炉格納容器、3
・・・弁、4・・・ブロワ、5・・・弁、6・・・主復
水器、7・・・空気抽出器、8・・・弁、9・・・升、
10・・・排ガス予熱器、11・・・排ガス再結合器、
12・・・排ガス復水器、13・・・活性炭吸着塔、1
4・・・排気筒、15・・・水素濃度測定器、16・・
・弁つ 第2図 −717
FIG. 1 is a flow sheet of one embodiment of the present invention, and FIG. 2 is a flow sheet of another embodiment. 1... Reactor pressure vessel, 2... Reactor containment vessel, 3
...Valve, 4...Blower, 5...Valve, 6...Main condenser, 7...Air extractor, 8...Valve, 9...Sho,
10... Exhaust gas preheater, 11... Exhaust gas recombiner,
12... Exhaust gas condenser, 13... Activated carbon adsorption tower, 1
4...Exhaust stack, 15...Hydrogen concentration measuring device, 16...
・Benttsu Figure 2-717

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉冷却材喪失事故時に発生する水素および酸素
ガスを原子炉格納容器内から抽気する装置と、原子炉の
通常運転時原子炉内に2ける炉水の放射線分解によって
発生する酸素水素ガスを処理する排ガス処理系再結合装
置において、原子炉冷却材喪失事故時に発生する酸素・
水素ガスを排ガス処理系再結合装置入口ラインに接続し
、排ガス処理設備再結合装置で酸素・水素を再結合はせ
ることを特徴とした酸素・水素再結合装置。
1. A device to bleed hydrogen and oxygen gas generated during a loss of reactor coolant accident from inside the reactor containment vessel, and 2. Oxygen hydrogen gas generated by radiolysis of reactor water in the reactor during normal operation of the reactor. In the exhaust gas treatment system recombination equipment that processes oxygen and
An oxygen/hydrogen recombination device characterized by connecting hydrogen gas to the exhaust gas treatment system recombination device inlet line and recombining oxygen and hydrogen in the exhaust gas treatment system recombination device.
JP57221845A 1982-12-20 1982-12-20 Oxygen.hydrogen recombiner Pending JPS59112295A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57221845A JPS59112295A (en) 1982-12-20 1982-12-20 Oxygen.hydrogen recombiner

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57221845A JPS59112295A (en) 1982-12-20 1982-12-20 Oxygen.hydrogen recombiner

Publications (1)

Publication Number Publication Date
JPS59112295A true JPS59112295A (en) 1984-06-28

Family

ID=16773084

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57221845A Pending JPS59112295A (en) 1982-12-20 1982-12-20 Oxygen.hydrogen recombiner

Country Status (1)

Country Link
JP (1) JPS59112295A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014115289A (en) * 2012-12-11 2014-06-26 Ge-Hitachi Nuclear Energy Americas Llc Radioactive capture system and method for containing severe accident of light water reactor (lwr)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014115289A (en) * 2012-12-11 2014-06-26 Ge-Hitachi Nuclear Energy Americas Llc Radioactive capture system and method for containing severe accident of light water reactor (lwr)
US9406407B2 (en) 2012-12-11 2016-08-02 Ge-Hitachi Nuclear Energy Americas Llc Radioactive capture system for severe accident containment of light water reactors (LWRS), and method thereof

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