JPH04104096A - Reactor container - Google Patents
Reactor containerInfo
- Publication number
- JPH04104096A JPH04104096A JP2219999A JP21999990A JPH04104096A JP H04104096 A JPH04104096 A JP H04104096A JP 2219999 A JP2219999 A JP 2219999A JP 21999990 A JP21999990 A JP 21999990A JP H04104096 A JPH04104096 A JP H04104096A
- Authority
- JP
- Japan
- Prior art keywords
- hydrogen
- reactor
- nuclear reactor
- reactor containment
- curtain
- 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
- 229910052739 hydrogen Inorganic materials 0.000 claims abstract description 92
- 239000001257 hydrogen Substances 0.000 claims abstract description 92
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims abstract description 91
- 239000012528 membrane Substances 0.000 claims description 13
- 239000000463 material Substances 0.000 claims description 12
- 238000001179 sorption measurement Methods 0.000 claims description 11
- 238000010521 absorption reaction Methods 0.000 claims description 3
- 239000000126 substance Substances 0.000 abstract description 7
- 238000002485 combustion reaction Methods 0.000 abstract description 6
- 238000007689 inspection Methods 0.000 abstract description 2
- 229910045601 alloy Inorganic materials 0.000 description 8
- 239000000956 alloy Substances 0.000 description 8
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- 239000007789 gas Substances 0.000 description 4
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000007257 malfunction Effects 0.000 description 3
- 229910052759 nickel Inorganic materials 0.000 description 3
- 229910052722 tritium Inorganic materials 0.000 description 3
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 150000002431 hydrogen Chemical class 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 101001052394 Homo sapiens [F-actin]-monooxygenase MICAL1 Proteins 0.000 description 1
- 229910000990 Ni alloy Inorganic materials 0.000 description 1
- 229910001069 Ti alloy Inorganic materials 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 102100024306 [F-actin]-monooxygenase MICAL1 Human genes 0.000 description 1
- 239000011358 absorbing material Substances 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000012466 permeate Substances 0.000 description 1
- 230000005855 radiation 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
-
- 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１
（産業上の利用分野）
本発明は、原子炉の事故時に発生する水素を除去し得る
原子炉格納装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention 1 (Industrial Application Field) The present invention relates to a nuclear reactor containment system capable of removing hydrogen generated during a nuclear reactor accident.
（従来の技術）
原子炉の事故時には、軽水型原子炉では放射線による水
の分解および炉心に使用する一ジルコニウム合金と水の
化学反応によって水素か発生し、ナトリウム型原子炉で
は、ナトリウムと水が化学反応し水素か発生する。発生
した水素は原子炉格納容器の内部に充満していくが、水
素濃度か約４％以上になると水素燃焼が起こり、原子炉
格納容器の健全性が脅かされる。このような場合には、
原子炉格納容器内の水素濃度が４％にならないように水
素を除去する必要がある。(Prior technology) In the event of a nuclear reactor accident, hydrogen is generated in light water reactors by the decomposition of water by radiation and the chemical reaction between the monozirconium alloy used in the reactor core and water, while in sodium reactors, sodium and water are generated. Chemical reaction generates hydrogen. The generated hydrogen fills the inside of the reactor containment vessel, but if the hydrogen concentration exceeds about 4%, hydrogen combustion will occur, threatening the integrity of the reactor containment vessel. In such a case,
It is necessary to remove hydrogen so that the hydrogen concentration within the reactor containment vessel does not reach 4%.
従来、原子炉の事故時に発生する水素は、第３図に示す
ような可燃性ガス濃度制御系で除去している。この可燃
性ガス濃度制御系は、原子炉圧力容器１を格納する原子
炉格納容器２にバルブ３を介して接続されるブロワ４、
加熱器５、再結合器６および冷却器７で構成されている
。これは、原子炉の事故時に原子炉格納容器２の内部に
充満した水素を、バルブ３を開きブロワ４を作動させる
ことによって加熱器５に送り込み、再結合器６て水にす
ることで水素を除去している。再結合器６て生成された
水は冷却器７を経て原子炉格納容器２内にバルブ３を介
して供給される。Conventionally, hydrogen generated during a nuclear reactor accident is removed using a combustible gas concentration control system as shown in FIG. This combustible gas concentration control system includes a blower 4 connected via a valve 3 to a reactor containment vessel 2 that houses a reactor pressure vessel 1;
It is composed of a heater 5, a recombiner 6, and a cooler 7. This works by opening a valve 3 and operating a blower 4 to send the hydrogen that filled inside the reactor containment vessel 2 at the time of a nuclear reactor accident to a heater 5, and converting it into water through a recombiner 6. It is being removed. The water produced in the recombiner 6 is supplied to the reactor containment vessel 2 via the valve 3 via the cooler 7 .
（発明が解決しようとする課題）
ところで、このような可燃性ガス濃度制御系は、装置が
複雑であるので価格が高い。また、装置を運転するには
、バルブ３、ブロワ４を作動させ、電力、冷却水を供給
する必要があることから、信頼性が低いという問題があ
った。(Problems to be Solved by the Invention) Incidentally, such a combustible gas concentration control system is expensive because the device is complicated. Further, in order to operate the device, it is necessary to operate the valve 3 and the blower 4 and to supply electric power and cooling water, so there is a problem of low reliability.
本発明は、このような点に対処してなされたもので、複
雑な装置を必要とすることなく水素を除去することがで
きる原子炉格納装置を提供することを目的とする。The present invention has been made in view of these problems, and an object of the present invention is to provide a nuclear reactor containment system that can remove hydrogen without requiring a complicated device.
［発明の構成コ
（課題を解決するための手段）
すなわち、本発明の原子炉格納装置は、水素吸着物質か
らなる水素吸収装置を原子炉格納容器内に配置、もしく
は水素透過膜を有する水素透過装置を原子炉格納容器に
配管接続してなるものである。[Configuration of the Invention (Means for Solving the Problems) In other words, the reactor containment system of the present invention includes a hydrogen absorption device made of a hydrogen adsorption material disposed in the reactor containment vessel, or a hydrogen permeation device having a hydrogen permeation membrane. The device is connected to the reactor containment vessel via piping.
（作 用）
本発明の原子炉格納装置においては、原子炉の事故時に
発生する水素を水素吸着物質に吸着させることによって
、あるいは水素透過膜からなる水素透過装置により選択
的に原子炉格納容器外に透過させることよって、原子炉
格納容器内の水素の充満を防ぐことができる。これによ
り、水素燃焼の発生を防止し、原子炉の安全性を向上す
ることができる。(Function) In the reactor containment system of the present invention, hydrogen generated during a nuclear reactor accident is selectively removed from the reactor containment vessel by being adsorbed by a hydrogen adsorbing material or by a hydrogen permeation device consisting of a hydrogen permeable membrane. By allowing hydrogen to pass through, it is possible to prevent the reactor containment vessel from being filled with hydrogen. This can prevent the occurrence of hydrogen combustion and improve the safety of the nuclear reactor.
（実施例）
以下、図面を参照して本発明の実施例を詳細に説明する
。なお、全ての図面において同一部分については同一符
号を付記した。(Example) Hereinafter, an example of the present invention will be described in detail with reference to the drawings. In addition, the same reference numerals are added to the same parts in all the drawings.
実施例１
第１図に本発明の、原子炉格納容器内に水素吸着物質か
らなる水素吸収装置を配置した原子炉格納装置の一実施
例を示す。本実施例では、原子炉圧力容器１を格納する
原子炉格納容器２内の上部にカーテンレール３が設置さ
れ、このカーテンレール３にカーテン取付具４を用いて
薄板状の水素吸着物質５か多数吊り下げられることによ
り、カーテンのごとくカーテンレール３に沿って移動可
能に配置される。このような水素吸着物質５からなる水
素吸収装置の形態は、普通の家屋の部屋のカーテンと同
様、種々の形状であってもよく、要は水素吸収物質５の
表面積を大きくし、原子炉運転中は原子炉格納容器２内
の空間に配置し、原子炉停止時には原子炉の点検作業に
支障のないように収納する。か取外すことが容易なもの
とする。Embodiment 1 FIG. 1 shows an embodiment of a reactor containment system according to the present invention, in which a hydrogen absorbing device made of a hydrogen adsorbing material is disposed inside the reactor containment vessel. In this embodiment, a curtain rail 3 is installed in the upper part of the reactor containment vessel 2 that houses the reactor pressure vessel 1, and a curtain rail 3 is attached to the curtain rail 3 using a curtain fixture 4. By being hung, it is movably arranged along the curtain rail 3 like a curtain. The form of the hydrogen absorbing device made of such a hydrogen absorbing material 5 may be in various shapes, similar to the curtains in a room in an ordinary house. The inside is placed in the space within the reactor containment vessel 2, and is stored so as not to interfere with reactor inspection work when the reactor is shut down. It shall be easy to remove.
以上のように構成することによって、原子炉格納容器２
内に生じた水素は、水素吸着物質５に接触して直ちにこ
れに吸着されるため、水素燃焼が起こる濃度まで上昇す
ることはない。By configuring as described above, the reactor containment vessel 2
Since the hydrogen generated in the hydrogen gas comes into contact with the hydrogen adsorption material 5 and is immediately adsorbed by it, the concentration does not rise to the point where hydrogen combustion occurs.
本発明で使用し得る水素を吸着する物質としては、チタ
ン合金、ニッケル合金等がある。現在開発されている水
素吸着合金は、合金１社当り ０，２ｍ３の水素を吸着
できるから、事故時に発生する水素量を１０００ｍ ３
とすると、５ｔｏｎ必要である。今後さらに水素吸着特
性の優れた材料が開発されれば、その量を減少させるこ
とができる。なお、水素吸着合金に関する文献として、
松原豊著“水素吸蔵合金”ＮＩＫＫＥＩ ＭＥＣ）ＩＡ
ＮＩＣＡＬ １９ｇ９．４．３ ＰＩＩＯ〜１１２があ
る。Examples of hydrogen adsorbing substances that can be used in the present invention include titanium alloys and nickel alloys. Currently developed hydrogen adsorption alloys can adsorb 0.2 m3 of hydrogen per alloy, so the amount of hydrogen generated in an accident can be reduced to 1000 m3.
Then, 5 tons are required. If materials with even better hydrogen adsorption properties are developed in the future, the amount can be reduced. In addition, as a literature regarding hydrogen adsorption alloys,
Yutaka Matsubara “Hydrogen storage alloy” NIKKEI MEC) IA
There is NICAL 19g9.4.3 PIIO~112.
このように本実施例においては、水素吸着物質５によっ
て水素を除去するという単純なシステムであるので、誤
動作の心配はなく信頼性が高い。In this way, in this embodiment, since the system is simple in that hydrogen is removed by the hydrogen adsorbing material 5, there is no fear of malfunction and the system is highly reliable.
また、水素吸着物質５をカーテン状にすることによって
表面積を大きくとることができ、水素吸着効率が高い。Further, by forming the hydrogen adsorbing material 5 into a curtain shape, the surface area can be increased, and hydrogen adsorption efficiency is high.
ｌｌ１１ｍ厚さの水素吸着合金は秒オーダーで水素を吸
着するのに対し、事故時の水素発生が日オーダーである
ことから、水素吸着合金を薄板とすることで、発生した
水素を十分早く除去することができる。さらに、水素吸
着合金をカーテン状にすることによって収納および取外
しが容易であり、原子炉の運転および保守点検時に支障
とはならない。A hydrogen adsorption alloy with a thickness of 11 m can adsorb hydrogen in seconds, whereas hydrogen generation during an accident occurs on the order of a day, so by making the hydrogen adsorption alloy into a thin plate, the generated hydrogen can be removed quickly enough. be able to. Furthermore, by forming the hydrogen adsorption alloy into a curtain shape, it is easy to store and remove it, and it does not pose a problem during the operation and maintenance of the nuclear reactor.
実施例２
第２図に本発明の、原子炉格納容器に水素透過膜を有す
る水素透過装置を配管接続した原子炉格納装置の一実施
例を示す。この図に示すように、原子炉圧力容器１を格
納する原子炉格納容器２に水素透過装置１１が配管１２
によって接続される。Embodiment 2 FIG. 2 shows an embodiment of the reactor containment system according to the present invention, in which a hydrogen permeation device having a hydrogen permeation membrane is connected to the reactor containment vessel through piping. As shown in this figure, a hydrogen permeation device 11 is connected to a pipe 12 in a reactor containment vessel 2 that houses a reactor pressure vessel 1.
connected by.
水素透過装置１１の中には水素透過膜１３があり、この
水素透過膜１３を境にして水素透過装置１１の原子炉格
納容器２側と反対側に水素排気管１４が接続され、さら
に排気筒１５に接続される。Inside the hydrogen permeation device 11, there is a hydrogen permeation membrane 13, and a hydrogen exhaust pipe 14 is connected to the side of the hydrogen permeation device 11 opposite to the reactor containment vessel 2 side with this hydrogen permeation membrane 13 as a boundary, and an exhaust pipe 14 is connected to the hydrogen permeation device 11 on the side opposite to the reactor containment vessel 2 side. 15.
以上のように構成することによって、原子炉の事故時に
原子炉格納容器２内に生じた水素は、水素透過膜１３を
通って排気筒１５から放出される。With the above configuration, hydrogen generated in the reactor containment vessel 2 during a nuclear reactor accident passes through the hydrogen permeable membrane 13 and is released from the exhaust stack 15.
これによって、原子炉格納容器２内の水素濃度は水素燃
焼が起こるほど上昇することはない。また、本実施例は
水素透過物質によって水素のみを透過させるという単純
なシステムであるので経済的であると同時に、誤動作等
の恐れはなく、信頼性が非常に高い。As a result, the hydrogen concentration within the reactor containment vessel 2 does not rise to the extent that hydrogen combustion occurs. Furthermore, this embodiment is a simple system in which only hydrogen permeates through a hydrogen-permeable substance, so it is economical, and at the same time, there is no fear of malfunction, and it is highly reliable.
本発明において、水素のみを透過する水素透過膜１３と
してニッケル膜を使用することができる。In the present invention, a nickel membrane can be used as the hydrogen permeable membrane 13 that only transmits hydrogen.
ニッケル膜の場合は、膜の厚さ ０．５龍、膜の面積は
１０コ程度のものになる。このような水素透過装置１１
をコンパクトなものにするため、水素透過膜１３を第２
図に示すように波板とすることが実用的である。なお、
ニッケル膜は水素と同時にトリチウムも通過させるので
、排気筒１５を通して大気中に放出することによって拡
散させ、水素排気による放射線被爆が問題とならないよ
うにすることができる。また、原子炉事故時にはトリチ
ウム以外に気体中に放射性物質が混合しているが、これ
らの放射性物質は透過することなく外部に漏れる恐れは
ない。In the case of a nickel film, the thickness of the film is 0.5 mm, and the area of the film is about 10 mm. Such a hydrogen permeation device 11
In order to make the hydrogen permeable membrane 13 compact, the hydrogen permeable membrane 13 is
It is practical to use a corrugated plate as shown in the figure. In addition,
Since the nickel film allows tritium to pass through at the same time as hydrogen, it is possible to diffuse the tritium by releasing it into the atmosphere through the exhaust stack 15, so that radiation exposure due to hydrogen exhaust does not become a problem. Furthermore, during a nuclear reactor accident, radioactive substances other than tritium are mixed in the gas, but these radioactive substances do not pass through and there is no risk of them leaking outside.
［発明の効果］
以上の説明からも明らかなように、本発明によれば、簡
単な装置で原子炉の事故時に発生する水素を選択的に除
去することができ、原子炉格納容器内に水素か充満して
水素燃焼を起こすという危険性を排除することができる
。また、本発明は最近の目覚ましい材料技術の進歩を取
入れたもので、材料の性質をうまく活用したものである
。したがって、装置の誤動作の可能性が全くなく、信頼
性が非常に高い。さらに、簡単な装置であるため経済的
である。[Effects of the Invention] As is clear from the above explanation, according to the present invention, hydrogen generated during a nuclear reactor accident can be selectively removed with a simple device, and hydrogen can be removed in the reactor containment vessel. This eliminates the risk of hydrogen burning due to overfilling. Furthermore, the present invention incorporates recent remarkable advances in material technology and makes good use of the properties of the materials. Therefore, there is no possibility of malfunction of the device, and reliability is very high. Furthermore, since it is a simple device, it is economical.
第１図は本発明の、原子炉格納容器内に水素吸着物質か
らなる水素吸収装置を配置した原子炉格納装置の一実施
例を概略的に示す図、第２図は本発明の、原子炉格納容
器に水素透過膜を有する水素透過装置を配管接続した原
子炉格納装置の一実施例を概略的に示す図、第３図は従
来例を示すブロック図である。
１・原子炉圧力容器、２・・原子炉格納容器、３・・・
カーテンレール、４・・・カーテン取付具、５・・・水
素吸着物質、１１・・・水素透過装置、１３・・・水素
透過膜、１４・水素排気管、１５・・・排気筒代理人
弁理士 則 近 憲 佑
第 １ ズ
第２図FIG. 1 is a diagram schematically showing an embodiment of a nuclear reactor containment system according to the present invention, in which a hydrogen absorption device made of a hydrogen adsorbing material is disposed inside the reactor containment vessel, and FIG. FIG. 3 is a diagram schematically showing an embodiment of a nuclear reactor containment system in which a hydrogen permeation device having a hydrogen permeation membrane is connected to a containment vessel through piping, and FIG. 3 is a block diagram showing a conventional example. 1. Reactor pressure vessel, 2.. Reactor containment vessel, 3..
Curtain rail, 4...Curtain fixture, 5...Hydrogen adsorption material, 11...Hydrogen permeation device, 13...Hydrogen permeation membrane, 14.Hydrogen exhaust pipe, 15...Exhaust stack agent
Patent Attorney Rules Kensuke Chika Part 1 Figure 2
Claims (2)
素吸着物質からなる水素吸収装置を配置したことを特徴
とする原子炉格納装置。(1) A reactor containment system characterized in that a hydrogen absorption device made of a hydrogen adsorption material is disposed within a reactor containment vessel that stores a reactor pressure vessel.
透過膜を有する水素透過装置を配管接続したことを特徴
とする原子炉格納装置。(2) A reactor containment system, characterized in that a hydrogen permeation device having a hydrogen permeation membrane is connected via piping to a reactor containment vessel that stores a reactor pressure vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2219999A JPH04104096A (en) | 1990-08-23 | 1990-08-23 | Reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2219999A JPH04104096A (en) | 1990-08-23 | 1990-08-23 | Reactor container |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH04104096A true JPH04104096A (en) | 1992-04-06 |
Family
ID=16744348
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2219999A Pending JPH04104096A (en) | 1990-08-23 | 1990-08-23 | Reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH04104096A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH11166996A (en) * | 1997-12-04 | 1999-06-22 | Toshiba Corp | Hydrogen removing device of reactor containment |
| JP2014115207A (en) * | 2012-12-11 | 2014-06-26 | Hitachi-Ge Nuclear Energy Ltd | Hydrogen removal facility for nuclear reactor building |
| JP2021085716A (en) * | 2019-11-26 | 2021-06-03 | 日立Ｇｅニュークリア・エナジー株式会社 | Hydrogen processing system |
-
1990
- 1990-08-23 JP JP2219999A patent/JPH04104096A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH11166996A (en) * | 1997-12-04 | 1999-06-22 | Toshiba Corp | Hydrogen removing device of reactor containment |
| JP2014115207A (en) * | 2012-12-11 | 2014-06-26 | Hitachi-Ge Nuclear Energy Ltd | Hydrogen removal facility for nuclear reactor building |
| JP2021085716A (en) * | 2019-11-26 | 2021-06-03 | 日立Ｇｅニュークリア・エナジー株式会社 | Hydrogen processing system |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP6876447B2 (en) | Nuclear power plant | |
| JP6798912B2 (en) | Reactor containment vent system | |
| WO2021227466A1 (en) | Passive hydrogen elimination device and hydrogen elimination system for nuclear power plant | |
| CN103890858B (en) | Trap the equipment of the fuel gas produced by the radiolysis in confined space or pyrolysis | |
| US3041134A (en) | Method of removing gaseous fission products from gases | |
| JPH04104096A (en) | Reactor container | |
| US3993542A (en) | Process and apparatus for extraction of gases produced during operation of a fused-salt nuclear reactor | |
| US4687625A (en) | Piping of nuclear reactor containment vessel | |
| EP0360240B1 (en) | Method of restraining diffusion of tritium and apparatus for same | |
| JP2005003371A (en) | Method and device for removing hydrogen in reactor containment vessel | |
| JPH08184689A (en) | Power reactor provided with hydrogen producing mechanism | |
| KR101494074B1 (en) | Complex Apparatus Removable for Airborne Radioactive Materials | |
| EP0730279A1 (en) | Method and apparatus for non-catalytic oxidation of tritium, and system for removing tritium | |
| Penzhorn | Tritium storage | |
| JP2743087B2 (en) | Reactor | |
| Moore | Control technology for radioactive emissions to the atmosphere at US Department of Energy facilities | |
| JPH0293399A (en) | Tritium remover | |
| Pierce et al. | Handling of tritium at TFTR | |
| JPH1194979A (en) | Containment vent equipment | |
| Haroldsen | HERMETIC SEALING PROBLEMS IN A SMALL BOILING WATER REACTOR | |
| JPH04299300A (en) | Chamber for housing fusion reactor or tritium handling device | |
| JPS58210598A (en) | Emergency tritium absorbing device | |
| Kirch et al. | Control of the tritium path in process heat HTR's | |
| Caldwell-Nichols et al. | Decontamination, dismantling and refurbishing of the PETRA glove box at the tritium laboratory, karlsruhe | |
| CHEEVER | NEW AIR CLEANING ACTIVITIES AT ARGONNE NATIONAL LABORATORY |