JPH0318795A - Reactor - Google Patents
ReactorInfo
- Publication number
- JPH0318795A JPH0318795A JP1154042A JP15404289A JPH0318795A JP H0318795 A JPH0318795 A JP H0318795A JP 1154042 A JP1154042 A JP 1154042A JP 15404289 A JP15404289 A JP 15404289A JP H0318795 A JPH0318795 A JP H0318795A
- Authority
- JP
- Japan
- Prior art keywords
- gas
- moderator
- reactor
- hydrogen
- deuterium
- 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.)
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Links
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
(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】
〔産業上の利用分野〕
本発明は、重水または軽水を減速材とする原子炉減速材
カバーガス装置を備えた原子炉に係り、特に、減速材の
放射線分解による酸素発生を防止するのに好適な原子炉
減速材カバーガス装置を備えた原子炉に関する。Detailed Description of the Invention [Industrial Application Field] The present invention relates to a nuclear reactor equipped with a reactor moderator cover gas device that uses heavy water or light water as a moderator. The present invention relates to a nuclear reactor equipped with a reactor moderator cover gas device suitable for preventing nuclear power generation.
(従来の技術〕
従来、原子炉減速材カバーガス装置は、減速材の劣化防
止を目的とし、かつ,カバーガスとしては、原子炉近傍
の放射線密度の高い領域で使用されるため、化学的に安
定で放射化されにくい不活性ガスが用いられている.
また、重水又は軽水を減速材とする原子炉では,放射線
によって減速材が分解され,重水素又は水素(以下水素
という)と酸素が発生し、カバーガス中へ放出される。(Conventional technology) Conventionally, reactor moderator cover gas devices have been designed to prevent deterioration of the moderator, and since the cover gas is used in areas with high radiation density near the reactor, chemically An inert gas is used that is stable and difficult to activate.In addition, in nuclear reactors that use heavy water or light water as a moderator, the moderator is decomposed by radiation, producing deuterium or hydrogen (hereinafter referred to as hydrogen) and oxygen. and is released into the cover gas.
この際、カバーガス中の水素及び酸素濃度がある範囲内
になると,水素と酸素は激しく反応し、水素爆発を起こ
す。このため、「発電用原子力設備の技術基準」 (通
産省令)の解説(通産省資源エネルギー庁、公益事業部
原子力発電安全管理課編)では、第32条原子炉格納容
器施設等の項で,原子炉格納容器内の水素濃度が4%未
満であることおよびまたは酸素濃度が5%未満であるこ
ととしている。At this time, when the hydrogen and oxygen concentrations in the cover gas fall within a certain range, hydrogen and oxygen react violently, causing a hydrogen explosion. For this reason, in the commentary on the "Technical Standards for Nuclear Power Generation Equipment" (Ordinance of the Ministry of International Trade and Industry) (edited by the Agency for Natural Resources and Energy, Ministry of International Trade and Industry, Nuclear Power Generation Safety Management Division, Public Utilities Department), Article 32, Reactor Containment Vessel Facilities, etc. It is assumed that the hydrogen concentration in the reactor containment vessel is less than 4% and/or the oxygen concentration is less than 5%.
また、可燃性ガスと空気(又は酸素)の混合物において
、可燃性ガスの濃度が低すぎても高すぎても火炎の伝播
が起こらなくなる濃度限界が現われる。水素又は重水素
の爆発範囲は,4〜75vofl%であり、水素濃度が
4voQ%以下では、水素爆発は生じないことがビュー
ローオブマインズBureau of MinesのZ
abetakis著の「可燃ガスおよび蒸気の燃焼特性
Flamma−bilityCharacterist
ics of Combustible Gases
andVapours (1965) Jに発表されて
いる。Furthermore, in a mixture of flammable gas and air (or oxygen), a concentration limit appears where flame propagation no longer occurs, whether the concentration of flammable gas is too low or too high. The explosive range of hydrogen or deuterium is 4 to 75 vofl%, and the Bureau of Mines' Z
"Flamma-bility Characterist of Combustible Gases and Steam"
ics of Combustible Gases
andVapours (1965) published in J.
上述のことから、原子炉減速材カバーガス装置には、再
結合器等の水素、酸素の処理設備が設けられ、カバーガ
ス中の水素、酸素の濃度が所定の値以下に保持されてい
る。From the above, the reactor moderator cover gas device is provided with hydrogen and oxygen processing equipment such as a recombiner, and the concentrations of hydrogen and oxygen in the cover gas are maintained at predetermined values or below.
例えば、重水を減速材とする新型転換炉では、原子炉減
速材カバーガス装置として、ヘリウムを循環させる装置
が採用されている。本装置(以下本系統という)は,カ
ランドリアタンク(減速材保有タンク)、重水冷却系、
重水浄化系及びその他の重水系機器内にカバーガスとし
てヘリウムを循環させて重水の劣化を防止するとともに
、重水の放射線分解によって生ずる重水素,酸素の爆発
性気体を再結合させて重水に戻し,プラントを安金な状
態に維持する。本系統の概要を第2図に、また原理図を
第3図に示す.
本系統は,ブロア1 (4台内2台予備)と、該ブロア
1の吐出側に、吐出弁1oを介して接続された2台のブ
ロア用セパレータ2と,該ブロア用セパレータ2の出口
側に予熱器入口弁l1を介して接続された2台のヘリウ
ムガス予熱器3と、該ヘリウムガス予熱器3それぞれの
出口側に予熱器出口弁12を介して接続された2台の再
結合器4と、該再結合器4それぞれの出口側に再結合器
出口弁13を介して接続された2台の冷却器5と,該冷
却器5の出口側を冷却器出口弁l4を介してカランドリ
アタンク9の減速材(重水)液面上の部分に接続するカ
バーガス戻し管l5と,前記ブロア1の入口側とカラン
ドリアタンク9の減速材液面上の部分とを吸込弁17を
介して接続するカバーガス取出管16と,を備えている
.上記構或の本系統においては、カランドリアタンク9
内に減速材(重水)18のカバーガスとして充填されて
いるヘリウムガスは,カバーガス取出管16、吸込弁1
7を経て、ブロア1へ吸込まれ、該ブロア1から吐出さ
れたヘリウムガスは混入した前記ブロアlの封水重水を
ブロア用セパレータ2で除去される。ブロア用セバレー
タ2を出たヘリウムガスは、次いで、ヘリウムガス予熱
器3で予熱された後、再結合器4に導かれ,放射線分解
によって生じたヘリウム中の重水素、酸素が、該再結合
器4中の触媒により、再結合されて重水になる。結合熱
によって昇温されたヘリウムガスは冷却器5で冷却され
たのち、カバーガス戻し管15により、前記カランドリ
アタンク9の減速材液面上に戻される.
本系統は,原子炉運転中、カバーガス中の重水素濃度を
3 no Q%程度以下とし,ブロア1が1台停止して
も予備機を起動してカバーガス中の重水素濃度を爆発限
界以下に保ち、水素爆発を防止して、原子炉の安全運転
を維持している.また、特開昭61−260195号公
報に記載の発明では、第4図に示すようにカバーガスと
して純粋な水素ガスを用いることにより、カバーガスの
水素濃度を水素の爆発範囲以上とし、水素爆発を防止す
るとともに、放射線分解によって発生した酸素を即時に
水素と再結合させ、カバーガス(気相)への酸素放出を
低減している。For example, in a new converter reactor that uses heavy water as a moderator, a device that circulates helium is used as a reactor moderator cover gas device. This equipment (hereinafter referred to as this system) consists of a calandria tank (tank containing moderator), a heavy water cooling system,
Helium is circulated as a cover gas in the heavy water purification system and other heavy water-based equipment to prevent deterioration of heavy water, and the explosive gases of deuterium and oxygen produced by radiolysis of heavy water are recombined and returned to heavy water. Keep the plant cheap. An overview of this system is shown in Figure 2, and a diagram of its principle is shown in Figure 3. This system consists of a blower 1 (2 out of 4 spares), two blower separators 2 connected to the discharge side of the blower 1 via a discharge valve 1o, and an outlet side of the blower separator 2. two helium gas preheaters 3 connected to each other via a preheater inlet valve l1, and two recombiners connected to each outlet side of the helium gas preheater 3 via a preheater outlet valve 12. 4, two coolers 5 connected to the outlet sides of the recombiners 4 via recombiner outlet valves 13, and two coolers 5 connected to the outlet sides of the coolers 5 via the cooler outlet valves l4. A cover gas return pipe 15 connected to the portion of the calandria tank 9 above the moderator (heavy water) liquid level is connected to the inlet side of the blower 1 and the portion of the calandria tank 9 above the moderator liquid level via the suction valve 17. The cover gas outlet pipe 16 is connected to the cover gas outlet pipe 16. In this system with the above structure, the calandria tank 9
Helium gas, which is filled as a cover gas for the moderator (heavy water) 18, is supplied to the cover gas outlet pipe 16 and the suction valve 1.
7, the helium gas is sucked into the blower 1, and the helium gas discharged from the blower 1 is removed from the heavy water sealed in the blower 1 by a blower separator 2. The helium gas that has exited the blower separator 2 is then preheated in a helium gas preheater 3 and then guided to a recombiner 4, where deuterium and oxygen in the helium produced by radiolysis are transferred to the recombiner. By the catalyst in 4, it is recombined to become heavy water. The helium gas heated by the heat of binding is cooled by the cooler 5 and then returned to the moderator liquid level in the calandria tank 9 through the cover gas return pipe 15. This system keeps the deuterium concentration in the cover gas below about 3 no Q% during reactor operation, and even if one blower 1 stops, the standby unit is activated to keep the deuterium concentration in the cover gas at the explosive limit. We maintain safe operation of the reactor by maintaining the following conditions to prevent hydrogen explosions. Furthermore, in the invention described in JP-A No. 61-260195, as shown in FIG. 4, by using pure hydrogen gas as the cover gas, the hydrogen concentration of the cover gas is made to be above the hydrogen explosion range, and a hydrogen explosion is caused. At the same time, the oxygen generated by radiolysis is immediately recombined with hydrogen, reducing the release of oxygen into the cover gas (gas phase).
第2図に示す上記従来技術では、再結合器等の(重)水
素・酸素の処理設備が設けられているが、設備費及び運
転費等のコスト及び運転操作性の点で問題があった。In the above conventional technology shown in Figure 2, processing equipment for (heavy) hydrogen and oxygen such as a recombiner is provided, but there are problems in terms of equipment costs, operating costs, etc., and operational operability. .
これを改善する対策として,第4図に示す特開昭61−
260195号公報記載の発明が提案されているが、こ
の発明では、カバーガスとして純粋の(重)水素ガスが
使用されているため、水素ガス供給設備が必要であると
ともに、メンテナンス等により水素を排気する際に、水
素ガス濃度が爆発範囲とならないよう、取扱いに注意を
要する。As a countermeasure to improve this, we have proposed a method for unexamined patent application published in 1986, as shown in Fig. 4.
The invention described in Publication No. 260195 has been proposed, but since pure (deuterium) hydrogen gas is used as the cover gas, hydrogen gas supply equipment is required, and hydrogen must be exhausted during maintenance etc. When handling, care must be taken to ensure that the hydrogen gas concentration does not reach the explosive range.
本発明の課題は、上記の水素ガス供給設備の容量削減及
びカバーガスの取扱い性の向上を図りつつ、放射線分解
による(重)水素及び酸素の発生量を低減し、原子炉減
速材カバーガス装置の容量(特に、再結合器容量)を削
減するにある。The object of the present invention is to reduce the amount of (heavy) hydrogen and oxygen generated by radiolysis while reducing the capacity of the hydrogen gas supply equipment described above and improving the handling of the cover gas. The goal is to reduce the capacity (especially the recombiner capacity).
上記の課題は重水もしくは軽水からなる原子炉減速材と
ともに該原子炉減速材の表面をおおう減速材カバーガス
を内包する容器を備えた原子炉の,減速材カバーガスを
不活性ガスと重水素もしくは不活性ガスと水素の混合ガ
スとし,該混合ガス中の重水素もしくは水素の濃度を水
素爆発限界以下とし、前記混合ガスの圧力を1気圧を超
える圧力とすることにより達成される。The above-mentioned problem is solved by a nuclear reactor equipped with a reactor moderator consisting of heavy water or light water and a container containing a moderator cover gas that covers the surface of the reactor moderator. This is achieved by using a mixed gas of an inert gas and hydrogen, setting the concentration of deuterium or hydrogen in the mixed gas to be below the hydrogen explosion limit, and setting the pressure of the mixed gas to a pressure exceeding 1 atmosphere.
上記の課題は、また、原子炉減速材と原子炉減速材カバ
ーガスとを内包する容器の気相部の圧力を1気圧を超え
る圧力に保持する手段を有する請求項1に記載の原子炉
によっても達成される。The above problem is also solved by the nuclear reactor according to claim 1, which has means for maintaining the pressure in the gas phase of the container containing the reactor moderator and the reactor moderator cover gas at a pressure exceeding 1 atmosphere. is also achieved.
上記の課題はさらに、原子炉減速材と原子炉減速材カバ
ーガスとを内包する容器の気相部に接続してデオキソ装
置が設けられている請求項上または2に記載の原子炉に
よっても達成される。The above object is further achieved by the nuclear reactor according to claim 1 or 2, wherein a deoxo device is provided connected to the gas phase part of the container containing the reactor moderator and the reactor moderator cover gas. be done.
上記の課題は、また、原子炉減速材と原子炉減速材カバ
ーガスとを内包する容器の気相部に接続して送風装置が
設けられ、該送風装置の吐出側は前記容器の液相部に接
続されている請求項1または2に記載の原子炉によって
も達威される。The above problem can also be solved by providing a blower device connected to the gas phase portion of the container containing the reactor moderator and the reactor moderator cover gas, and the discharge side of the blower device being connected to the liquid phase portion of the container. This can also be accomplished by a nuclear reactor according to claim 1 or 2, which is connected to a nuclear reactor.
上記の課題はさらに、原子炉減速材カバーガス中の重水
素もしくは水素の濃度を爆発限界以下とし、前記原子炉
減速材カバーガスの圧力を高めることにより原子炉減速
材中の溶存重水素もしくは溶存水素の濃度を高め,原子
炉減速材の放射線分解による酸素ガスの発生を抑制する
方法によっても達成される。The above problem can be further solved by reducing the concentration of deuterium or hydrogen in the reactor moderator cover gas to below the explosion limit and by increasing the pressure of the reactor moderator cover gas. This can also be achieved by increasing the concentration of hydrogen and suppressing the generation of oxygen gas due to radiolysis of the reactor moderator.
減速材である水分子に、中性子あるいはガンマ線が照射
されると,コンプトン散乱、光電効果により水分子の軌
道電子がはじき出される。この電子ははじき出された当
初は高いエネルギを持ち、高速であるが、電磁的相互作
用により極めて小さな領域で、エネルギを失い他の水分
子を電離する。When water molecules, which are moderators, are irradiated with neutrons or gamma rays, the orbital electrons of the water molecules are ejected by Compton scattering and the photoelectric effect. These electrons initially have high energy and high speed when ejected, but due to electromagnetic interaction they lose energy and ionize other water molecules in an extremely small area.
これにより、水分子の電離反応、
D,O”’)D”+OD+e−a g
に引き続いて極めて短時間のうちにD,○D−?どが生
じる。その他、一次生戊物として、D2,Oが生じ、一
次生成物はさらに相互反応しあうことにより、O,,0
2−,Do.,Do,−,D,02などの分解生或種が
生じる。As a result, following the ionization reaction of water molecules, D, O"') D"+OD+e-a g, D, ○D-? What will happen? In addition, D2,O is produced as a primary product, and the primary products further react with each other, resulting in O,,0
2-, Do. , Do, -, D,02 and other decomposition products are produced.
一方,このような状態下にある減速材の表面をヘリウム
と重水素D2の高圧混合ガスでカバーすると、D2は重
水素D2の分圧に比例して減速材に溶解し、水面付近等
では、以下の素反応が生じる。On the other hand, if the surface of the moderator under such conditions is covered with a high-pressure mixed gas of helium and deuterium D2, D2 will dissolve in the moderator in proportion to the partial pressure of deuterium D2, and near the water surface, etc. The following elementary reactions occur.
各素反応は、
2D2+20D→2D20+2D
D 十02 →DO2
D +D02→D202
D20■ →2D○
となり、見掛け上、2D,+02→2D20が進行する
結果、酸素と反応する。上の反応で、○Dは、見掛け上
触媒として作用するが、炉心で生成したD20よが、
D202 ″ 20D
←
の平衡反応により、○Dの供給源となる。Each elementary reaction is 2D2+20D→2D20+2D D 102 →DO2 D +D02→D202 D20■ →2D○, and as a result of the apparent progression of 2D, +02→2D20, it reacts with oxygen. In the above reaction, ○D apparently acts as a catalyst, but D20 produced in the core becomes a source of ○D through the equilibrium reaction of D202 ″ 20D ← .
以上のように、減速材中の溶存水素濃度が高まると、減
速材の放射線分解によって発生した酸素が即時に水素と
再結合し、カバーガス(気相)への酸素放出が低減され
る。As described above, when the concentration of dissolved hydrogen in the moderator increases, oxygen generated by radiolysis of the moderator immediately recombines with hydrogen, reducing the release of oxygen into the cover gas (gas phase).
第1図により本発明の第1の実施例を説明する。 A first embodiment of the present invention will be explained with reference to FIG.
図に示す原子炉は,減速材である重水18と減速材カバ
ーガス19とを内包する容器である減速材保有タンク9
と、該減速材保有タンク9を上下方向に貫通して設けら
れた圧力管8と、該圧力管8に内装された核燃料7と、
を備えている。重水t8は、温度変動等による液面変動
を可能にするため,減速材保有タンク9に充満させず、
上部に空間を残してあり、該空間に減速材カバーガス(
以下カバーガスという)19が充填してある。The reactor shown in the figure has a moderator holding tank 9 which is a container containing heavy water 18 which is a moderator and a moderator cover gas 19.
, a pressure pipe 8 provided vertically penetrating the moderator storage tank 9, and a nuclear fuel 7 housed in the pressure pipe 8;
It is equipped with The heavy water T8 is not filled into the moderator holding tank 9, in order to allow the liquid level to fluctuate due to temperature fluctuations, etc.
A space is left at the top, and the moderator cover gas (
19 (hereinafter referred to as cover gas) is filled.
減速材保有タンク9の気相部には,気相部の圧力を1気
圧(絶対圧力)を超える圧力に保持する手段として、カ
バーガス供給管24、圧力調整弁22.23を介して,
高圧のヘリウムを内包する高圧容器20および高圧の重
水素を内包する高圧容器21がそれぞれ接続されている
。A gas phase portion of the moderator storage tank 9 is supplied with a cover gas supply pipe 24 and a pressure regulating valve 22, 23 as a means for maintaining the pressure of the gas phase portion at a pressure exceeding 1 atmosphere (absolute pressure).
A high-pressure vessel 20 containing high-pressure helium and a high-pressure vessel 21 containing high-pressure deuterium are connected to each other.
この原子炉においては、圧力管8内の核燃料から放出さ
れる中性子は、圧力管外の重水で減速されたのち、熱中
性子となって核燃料7の連鎖反応を生起させる。該連鎖
反応によって核燃料7に発生する熱は,圧力管8内を流
れる冷却材に伝達され、原子炉外へ、移送されて、所要
の目的に使用される。In this nuclear reactor, neutrons emitted from the nuclear fuel in the pressure tube 8 are decelerated by heavy water outside the pressure tube, and then become thermal neutrons, causing a chain reaction in the nuclear fuel 7. The heat generated in the nuclear fuel 7 by the chain reaction is transmitted to the coolant flowing in the pressure pipe 8, transferred outside the nuclear reactor, and used for a desired purpose.
カバーガス19は、ヘリウムと3moQ%の重水素とが
混合されたもので、圧力を前記圧力調整弁22.23に
より70kg/cd(絶対圧)に保持してある.このと
き,重水素ガスの分圧はカバーガス中の重水素ガスの濃
度が、3moQ%であるから、70X0.03=2.1
kg/cii
となり、特開昭61−260195号公報記載の純粋な
重水素ガスを大気圧でカバーガスとして用いた例に比べ
,重水中への重水素ガスの溶解度が約2倍以上となり、
重水中での重水素と酸素の再結合効果が向上する。この
ため、重水中およびカバーガス中の酸素濃度は低い値で
飽和状態となり、再結合器等の重水素、酸素処理設備を
用いることなく,カバーガスの酸素濃度が爆発限界以下
に保持される。The cover gas 19 is a mixture of helium and 3 moQ% deuterium, and the pressure is maintained at 70 kg/cd (absolute pressure) by the pressure regulating valves 22 and 23. At this time, since the concentration of deuterium gas in the cover gas is 3moQ%, the partial pressure of deuterium gas is 70X0.03=2.1
kg/cii, and the solubility of deuterium gas in heavy water is more than double that of the example described in JP-A-61-260195 in which pure deuterium gas was used as a cover gas at atmospheric pressure.
The recombination effect of deuterium and oxygen in heavy water is improved. Therefore, the oxygen concentration in the heavy water and the cover gas becomes saturated at a low value, and the oxygen concentration in the cover gas is maintained below the explosive limit without using deuterium and oxygen processing equipment such as a recombiner.
第5図に示す第2の実施例は、減速材保有タンク9の気
相部に,酸素を除去するデオキソ装置lOが接続され、
カバーガスエ9が減速材保有タンク9の気相部と,該デ
オキソ装置の間を循環するように構或されている。本実
施例においては、減速材の放射線分解によって生じた重
水素と酸素のうち、酸素のみが、デオキソ装110によ
り除去され、重水素ガスの濃度が上昇する。重水素ガス
の濃度が水素爆発限界を越えないように、図示されてい
ないカバーガス圧力調整手段により,カバーガスの圧力
が調整され、再結合の進行状態が調節される6本実施例
においては、再結合のための重水素として放射線分解に
より生じた重水素が用いられるので,重水素ガスの初期
充填の必要がない。In the second embodiment shown in FIG. 5, a deoxo device IO for removing oxygen is connected to the gas phase portion of the moderator holding tank 9.
The cover gas 9 is configured to circulate between the gas phase portion of the moderator holding tank 9 and the deoxo apparatus. In this embodiment, of deuterium and oxygen produced by radiolysis of the moderator, only oxygen is removed by the deoxo unit 110, and the concentration of deuterium gas increases. In order to prevent the concentration of deuterium gas from exceeding the hydrogen explosion limit, the pressure of the cover gas is adjusted by a cover gas pressure adjustment means (not shown), and the progress state of recombination is adjusted.6 In this embodiment, Since deuterium produced by radiolysis is used as deuterium for recombination, there is no need for initial filling of deuterium gas.
第6図は本発明の第3の実施例を示し、本図に示される
原子炉は減速材保有タンク9の上部にタンク上方に突出
する複数の管状突出部25を備え,該管状突出部25の
最上部が,カバーガスを内包する気相部を形成している
。該気相部にカバーガス取り出し管16、吸込弁17を
介して送風装置であるブロア1の吸込側が接続され、該
ブロア1の吐出側はカバーガス戻し管L5Aを介して減
速材保有タンク9の底面に接続されている。燃料を内装
した圧力管8は前記第1の実施例の場合と同様に装着さ
れているが、説明は省略する。FIG. 6 shows a third embodiment of the present invention, and the nuclear reactor shown in this figure is provided with a plurality of tubular protrusions 25 at the top of the moderator holding tank 9 that protrudes upward from the tank. The top of the gas phase forms the gas phase containing the cover gas. The suction side of a blower 1, which is an air blower, is connected to the gas phase section through a cover gas take-off pipe 16 and a suction valve 17, and the discharge side of the blower 1 is connected to the moderator storage tank 9 through a cover gas return pipe L5A. Connected to the bottom. The pressure pipe 8 containing fuel is installed in the same manner as in the first embodiment, but its explanation will be omitted.
本実施例においては、管状突出部25内の気相部に高圧
に保持されたカバーガスがブロア1により吸引されて、
減速材保有タンク9の底部減速材中に吹きこまれる。カ
バーガスが該タンク底部から管状突出部25の気相部へ
上昇していく過程で、カバーガス中の重水素が減速材中
に溶解して溶存重水素濃度が高まり、放射線分解による
発生酸素と重水素の再結合が速やかに行われる。In this embodiment, the cover gas held at high pressure in the gas phase inside the tubular protrusion 25 is sucked by the blower 1, and
The moderator is blown into the bottom moderator of the moderator holding tank 9. In the process of the cover gas rising from the bottom of the tank to the gas phase of the tubular protrusion 25, deuterium in the cover gas dissolves into the moderator, increasing the dissolved deuterium concentration, and causing the oxygen generated by radiolysis to increase. Deuterium recombination occurs quickly.
上記第1〜第3の実施例においては、再結合器を設けな
いので、設備が簡単であり、さらに減速材中で酸素と重
水素の再結合が行われるので、減速材中の溶存酸素濃度
が低くなり減速材に接する部材の腐食が低減される。ま
た、外部へカバーガスが漏洩した場合もカバーガス内の
重水素ガス濃度は4moQ%(水素爆発限界)以下であ
って漏洩後に水素爆発に至る恐れはない。In the first to third embodiments described above, since a recombiner is not provided, the equipment is simple, and furthermore, since oxygen and deuterium are recombined in the moderator, the concentration of dissolved oxygen in the moderator is As a result, corrosion of members in contact with the moderator is reduced. Further, even if the cover gas leaks to the outside, the deuterium gas concentration in the cover gas is below 4 moQ% (hydrogen explosion limit), and there is no risk of a hydrogen explosion after the leak.
本発明によれば、重水または軽水を減速材とする原子炉
で、減速材カバーガスを、不活性ガスと水素爆発限界以
下の濃度の重水素もしくは水素の混合ガスとし,該混合
ガス圧力を1気圧(絶対圧力)以上にして用いられるの
で、カバーガス中の重水素もしくは水素の濃度を高める
ことなく、減速材中の溶存重水素もしくは水素の濃度が
高まり、放射線分解によって生じる酸素を減速材中で,
重水素もしくは水素と再結合させて、カバーガス中に放
出される酸素ガス量を低減させることが可能となり、カ
バーガス中の重水素ましくは水素と酸素とを再結合させ
る再結合器の容量を低減もしくは省略して設備を簡単に
する効果がある。According to the present invention, in a nuclear reactor using heavy water or light water as a moderator, the moderator cover gas is a mixed gas of an inert gas and deuterium or hydrogen at a concentration below the hydrogen explosion limit, and the mixed gas pressure is 1. Since it is used at a pressure above atmospheric pressure (absolute pressure), the concentration of dissolved deuterium or hydrogen in the moderator increases without increasing the concentration of deuterium or hydrogen in the cover gas, and the oxygen generated by radiolysis is removed from the moderator. in,
It is possible to reduce the amount of oxygen gas released into the cover gas by recombining it with deuterium or hydrogen, and the capacity of the recombiner to recombine deuterium or hydrogen and oxygen in the cover gas. This has the effect of simplifying equipment by reducing or omitting it.
第1図は本発明の第1の実施例の断面図を含む系統図、
第2図、第3図および第4図は従来技術を示す断面図お
よび系統図、第5図は本発明の第2の実施例を示す断面
図を含む系統図で、第6図は本発明の第3の実施例を示
す断面図を含む系統図である。
1・・・送風装置(ブロア)、9・・・容器(減速材保
有タンク)、10・・・デオキソ装置、18・・・減速
材、19・・・カバーガス、20.21・・・高圧容器
、22,23・・・圧力調整弁。FIG. 1 is a system diagram including a sectional view of the first embodiment of the present invention;
2, 3, and 4 are sectional views and system diagrams showing the prior art, FIG. 5 is a system diagram including a sectional view showing a second embodiment of the present invention, and FIG. 6 is a system diagram including a sectional view showing the second embodiment of the present invention. FIG. 3 is a system diagram including a cross-sectional view showing a third embodiment of the present invention. 1... Air blower (blower), 9... Container (tank holding moderator), 10... Deoxo device, 18... Moderator, 19... Cover gas, 20.21... High pressure Container, 22, 23...pressure regulating valve.
Claims (1)
原子炉減速材の表面をおおう減速材カバーガスを内包す
る容器を備えた原子炉において、減速材カバーガスが不
活性ガスと重水素もしくは不活性ガスと水素の混合ガス
であることと、該混合ガス中の重水素もしくは水素の濃
度が水素爆発限界以下であることと、前記混合ガスの圧
力が1気圧を超える圧力であることと、を特徴とする原
子炉。 2、原子炉減速材と原子炉減速材カバーガスとを内包す
る容器の気相部の圧力を1気圧を超える圧力に保持する
手段を有することを特徴とする請求項1に記載の原子炉
。 3、原子炉減速材と原子炉減速材カバーガスとを内包す
る容器の気相部に接続してデオキソ装置が設けられてい
ることを特徴とする請求項1または2に記載の原子炉。 4、原子炉減速材と原子炉減速材カバーガスとを内包す
る容器の気相部に接続して送風装置が設けられ、該送風
装置の吐出側は前記容器の液相部に接続されていること
を特徴とする請求項1または2に記載の原子炉。 5、原子炉減速材カバーガス中の重水素もしくは水素の
濃度を爆発限界以下とし、前記原子炉減速材カバーガス
の圧力を高めることにより原子炉減速材中の溶存重水素
もしくは溶存水素の濃度を高め、原子炉減速材の放射線
分解による酸素ガスの発生を抑制する方法[Claims] 1. In a nuclear reactor equipped with a reactor moderator made of heavy water or light water and a container containing a moderator cover gas that covers the surface of the reactor moderator, the moderator cover gas is an inert gas. and deuterium or an inert gas and hydrogen; the concentration of deuterium or hydrogen in the mixed gas is below the hydrogen explosion limit; and the pressure of the mixed gas exceeds 1 atmosphere. A nuclear reactor characterized by: 2. The nuclear reactor according to claim 1, further comprising means for maintaining the pressure in the gas phase of the container containing the reactor moderator and the reactor moderator cover gas at a pressure exceeding 1 atmosphere. 3. The nuclear reactor according to claim 1 or 2, further comprising a deoxo device connected to a gas phase portion of a container containing a reactor moderator and a reactor moderator cover gas. 4. A blower device is provided connected to the gas phase portion of the container containing the reactor moderator and the reactor moderator cover gas, and the discharge side of the blower device is connected to the liquid phase portion of the container. The nuclear reactor according to claim 1 or 2, characterized in that: 5. Lower the concentration of deuterium or hydrogen in the reactor moderator cover gas to below the explosion limit and increase the pressure of the reactor moderator cover gas to reduce the concentration of dissolved deuterium or hydrogen in the reactor moderator. A method to suppress the generation of oxygen gas due to radiolysis of nuclear reactor moderator
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1154042A JP2743087B2 (en) | 1989-06-16 | 1989-06-16 | Reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1154042A JP2743087B2 (en) | 1989-06-16 | 1989-06-16 | Reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0318795A true JPH0318795A (en) | 1991-01-28 |
| JP2743087B2 JP2743087B2 (en) | 1998-04-22 |
Family
ID=15575651
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1154042A Expired - Lifetime JP2743087B2 (en) | 1989-06-16 | 1989-06-16 | Reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2743087B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20000054723A (en) * | 2000-06-20 | 2000-09-05 | 조달현 | Method of advertisement in cigarette paper |
| JP2015152539A (en) * | 2014-02-18 | 2015-08-24 | 三菱重工業株式会社 | Moderation device and neutron irradiation apparatus |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61260195A (en) * | 1985-05-15 | 1986-11-18 | 株式会社日立製作所 | Cover gas system of moderator for nuclear reactor |
-
1989
- 1989-06-16 JP JP1154042A patent/JP2743087B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61260195A (en) * | 1985-05-15 | 1986-11-18 | 株式会社日立製作所 | Cover gas system of moderator for nuclear reactor |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20000054723A (en) * | 2000-06-20 | 2000-09-05 | 조달현 | Method of advertisement in cigarette paper |
| JP2015152539A (en) * | 2014-02-18 | 2015-08-24 | 三菱重工業株式会社 | Moderation device and neutron irradiation apparatus |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2743087B2 (en) | 1998-04-22 |
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