JPS5931497A - Depressing device for inside of reactor container - Google Patents
Depressing device for inside of reactor containerInfo
- Publication number
- JPS5931497A JPS5931497A JP57141941A JP14194182A JPS5931497A JP S5931497 A JPS5931497 A JP S5931497A JP 57141941 A JP57141941 A JP 57141941A JP 14194182 A JP14194182 A JP 14194182A JP S5931497 A JPS5931497 A JP S5931497A
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- reactor
- reactor containment
- pressure
- discharge pipe
- 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.)
- Granted
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】
〔発明の技術分野〕
本発明は事故時に原子炉格納容器内で発生する水系等の
可燃性ガスを安全に外部に放出し、原子炉格納容器内の
圧力上列を防止１−る原子炉格納容器内減圧装置に関１
−る。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention safely discharges flammable gas such as water generated within the reactor containment vessel to the outside in the event of an accident, and relieves pressure in the reactor containment vessel. Prevention 1 - Concerning depressurization equipment inside the reactor containment vessel 1
-ru.
沸騰水形原子炉等の軽水炉は、原子炉格納容器内に原子
炉圧力容器を収容し、万−冷却拐等の漏洩が生じた場合
に放射性物知が外部に拡散するのを防止するように構成
されている。また、この原子炉格納容器内は圧力抑制室
が設けられており、尚温筒圧の冷却材が漏洩した場合に
はこの蒸気を圧力抑制室内に放出してＷ Ｋｍさせ、原
子炉格納容器内の内圧上昇を防止している。Light water reactors such as boiling water reactors house a reactor pressure vessel within the reactor containment vessel to prevent radioactive material from dispersing outside in the event of a leak such as cooling loss. It is configured. In addition, a pressure suppression chamber is installed inside the reactor containment vessel, and in the event that coolant at still hot cylinder pressure leaks, this steam is released into the pressure suppression chamber for W km, and the inside of the reactor containment vessel is This prevents the internal pressure from increasing.
そして、原子炉の事故時には、この原子ＩＰ）ｆ６粕容
器は外部から完全に隔離される。In the event of a nuclear reactor accident, this atomic IP) f6 lees container is completely isolated from the outside.
冷却杓の漏出が生した場合１−なわち冷却材喪失事故を
想定した場合、過熱したジルコニウム合金製の燃料被覆
管とＧ却材（４１水）とが反応して水素等の内燃１ｑニ
ガスが発生１゛ることか予想される。また、冷却拐の放
射相分解によって水素、酸素等の可燃性ガスが発生する
ことも予想される。ところで、この上うな可燃性ガスは
非凝癲性であるため、圧力仰制呈で凝縮することはでき
ず、原子炉格納容器内に蓄積されてゆく。In case of leakage of the cooling scoop 1 - In other words, assuming a loss of coolant accident, the overheated zirconium alloy fuel cladding tube reacts with the G refrigerant (41 water) and 1q of internal combustion gas such as hydrogen is generated. It is expected that this will occur once. It is also expected that flammable gases such as hydrogen and oxygen will be generated due to the radiation phase decomposition of the cooling process. Incidentally, since such flammable gases are non-condensable, they cannot be condensed due to pressure rise and accumulate in the reactor containment vessel.
このため、原子炉格納容器内の圧力が上昇し、このル（
子炉イ・６粕容器から外＋′ｊ＋＞への漏洩が生じるｇ
Ｊ’ ｔｉ：：性がある。また、カー原子＄−ｊ格納谷
器内でこの１」ツ、（？ミ性ガスか燃焼した場合には原
子炉６１内１ｈＡ−・内ｔ１５の機器の健全伯コに悪影
響を与える司能仁もある。As a result, the pressure inside the reactor containment vessel increases, and this
Child furnace A/6 Leakage occurs from the lees container to the outside
J' ti:: There is sex. In addition, if this 1" (?) gas were to burn in the containment vessel of the nuclear reactor 61, it would have an adverse effect on the health of the equipment in the reactor 61. be.
木兄１夕］の目的は原士炉格ｔ４Ｉｌ谷器内【ζ蓄積し
た可燃１１１゛ガスな安全に外部に放出し、原子炉格納
容凍、内の圧力上昇を防止し、またこα〕原子炉格納谷
器内でのｌ′ＪＪ燃１」ユガスの燃蓼″已を防止するこ
とかでさる原子炉格納容器内減圧装置を１灯ることにあ
る。The purpose of the nuclear reactor was to safely release the accumulated flammable 111 gas to the outside, prevent the pressure from rising inside the reactor, and The purpose of this project is to turn on one light in the pressure reducing device inside the reactor containment vessel in order to prevent l'JJ fuel from burning inside the reactor containment vessel.
不発ゆ」は−１’に１ｉが原子炉格納容器内に連通し他
節。が外気に１ｊｉｊ放された放出管も・設け、この放
出音の連中にはυ＋’Ｊ Ｉ＝ｉｌ−］−Ｊｆ−を設げ
、また放出音の他端）７１Ｓにはこの放出管から放出さ
れるｄ］燃性ガスを燃焼させる燃焼機構を設けたもので
ある。した澱ｆつ・て、原子炉格納容器内にＥＩＪ燃件
ガスが苗挟した場合に＆ｊ、この＆ｌ開閉弁開方し、こ
の原子炉格納容器内のｏＪ箭、１１Ｌガスを燃焼機構で
燃焼させて安全に夕１都へ放出し、原子炉格納、１７：
ｉｓ内の圧力上昇を防止するとともに可燃性カスの換
反を燃焼脈１ｒ’以↑Ｉ／Ｃド１ｊ割して原子炉圧力容
器内部での可燃性ガスの燃焼を防止するものである。"Unexploded" means -1' and 1i are connected to the reactor containment vessel. A discharge pipe is also provided in which 1 jij is released into the outside air, and υ+'J I=il-]-Jf- is provided for those who are emitting this sound, and the other end of the emitted sound is emitted from this pipe. d] A combustion mechanism is provided to combust the combustible gas. When EIJ combustion gas is trapped inside the reactor containment vessel, the &l on-off valve is opened and the 11L oJ gas in the reactor containment vessel is combusted by the combustion mechanism. Safely released to Tokyo in the evening and stored in the reactor, 17:
This is to prevent the pressure rise in the reactor pressure vessel and to prevent the combustion of combustible gas inside the reactor pressure vessel by dividing the exchange of flammable gas by ↑I/C de 1j from the combustion pulse 1r'.
〔発甲」の実施２例〕
す、Ｔ−図を＃ ＩＫ−ｔ、て本発明の一犬施拘１を説
明する。図中１は原子炉建屋であって、この原子炉６１
内には原子炉格納容器２が設けられている。そして、こ
σ）ｊあ１子炉格稍台器２内には原子炉圧力容器３か収
容されており、この原子炉出力Ｍ ’ｉ！’ｉｔ Ｊ内
には炉′心（図示せず）がｊ反答されている。そして、
この原子炉圧力容器３内の冷却拐は円やｉ均【ポンプ４
，４によって循ま泉されるように構成されている。そし
て、この原子炉格納容器２には原子ｆ格稍谷器内減圧装
置ｊ’ｆ５か接続されており、以−ドこの原子炉格納容
器内減圧装置５の構成を説明する・
図中６は放出管であって、その一端は原子炉格納容器２
内に連通し、また他端はスタック７の上端まで尋ひかれ
、こσ）スタック７の上１７ｊｉａにおいて大気にυト
］放されているＯまた、上記原子炉建屋Ｉ内の放出管６
には１４１閉うｆ８が設けられている。また、このＶ旧
防升８のＦ流側にはバイパス弁９が設けられている。そ
して、このバイパスプ「９と並列に放射性物負処理磯４
’ｆｊ４７が設けられている。この数カ８：物纏処理機
構１０は放射性物穎除去器１１をｉｎｈえ、この放射性
物責除云Ｚ３１１の上流１則にはポンプ１２が設けられ
、さらにこのポンプＩ２の上流側および放射性拘留除去
器ＩＩのＴ所、■（０には入口弁１３および出口弁Ｉ４
が設けられている。また、上記放出管６の他端部には燃
焼ｅ ｐ７ｆ； ７ ｓが設けられている・この燃焼機
構ｔｓｂ＝、放出管６から放出される内燃１（１カスに
点火し、この可燃性ガスを弓虫制的に燃焼させるように
構成されている。また、この燃焼機構１５の上流１１１
１１に（」炎伝播遮断器Ｉ６が設けられており、燃９ト
（勉構１５で燃焼した炎がこの放出管６内を上流側に伝
播するのを防止１−るように構成されている。また、こ
の放出管６の一端部には不活性ガス注入他構Ｌ１が設け
られている。この不活性ガス注入機構圧は窒素等の不活
性なガスを供給する不活性ガス供給源１８を備えており
、この不活性ガス供給源１８は壮入升１９，１９を介し
て放出音６σ）一端部に接続されている。また、上記原
子炉格納容器２内には圧力検出器２０および放射縁検出
器２１が設けられている。そして、この圧力検出器２０
および放射線検出器２Ｚからの信匈は制御回路２２に送
られるように構成されている。[Second Examples of Implementation of Injection] One-dog enforcement 1 of the present invention will be explained using the T-diagram as #IK-t. 1 in the figure is the reactor building, and this reactor 61
A reactor containment vessel 2 is provided inside. The reactor pressure vessel 3 is housed in the reactor 2, and the reactor output M'i! 'it J' contains a reactor core (not shown). and,
This cooling inside the reactor pressure vessel 3 is yen or i [pump 4
, 4. The reactor containment vessel 2 is connected to the nuclear reactor containment vessel pressure reducing device j'f5, and the configuration of this reactor containment vessel pressure reducing device 5 will be explained below. A discharge pipe, one end of which is connected to the reactor containment vessel 2.
The other end is connected to the upper end of the stack 7, and is released to the atmosphere at the top 17jia of the stack 7. Also, the discharge pipe 6 in the reactor building I is
is provided with f8 that closes 141. Further, a bypass valve 9 is provided on the F flow side of this V old guard 8. And, in parallel with this bypass pump ``9'', there is a radioactive material negative processing island 4.
'fj47 is provided. This number 8: The material collection processing mechanism 10 is equipped with a radioactive material remover 11, and a pump 12 is provided upstream of this radioactive material removal device Z311, and further upstream of this pump I2 and radioactive material removal device 11 is installed. T position of remover II, ■ (0 has inlet valve 13 and outlet valve I4
is provided. Further, a combustion e p7f;7s is provided at the other end of the discharge pipe 6. This combustion mechanism tsb=ignites the internal combustion 1 (1 dregs) released from the discharge pipe 6, and burns the combustible gas. The upstream 111 of this combustion mechanism 15 is
11 is provided with a flame propagation interrupter I6, which is configured to prevent the flame combusted in the combustion chamber 15 from propagating upstream within this discharge pipe 6. Further, an inert gas injection mechanism L1 is provided at one end of the discharge pipe 6.The pressure of this inert gas injection mechanism is controlled by an inert gas supply source 18 that supplies an inert gas such as nitrogen. This inert gas supply source 18 is connected to one end of the emission sound 6σ) through the enclosures 19, 19. Also, inside the reactor containment vessel 2, there is a pressure detector 20 and a radiation An edge detector 21 is provided, and this pressure detector 20
The information from the radiation detector 2Z is also sent to the control circuit 22.
そして、この辺ａ１＋に１路２２は原子炉格納容器２内
の圧力が＝定の設定圧以上となった場合に開閉弁８を一
升し、さらにこの場合において原子炉格納容器２内の放
射線レベルが低い場合には第２図に示す如くバイパス弁
９を開弁するとともに放射性物貿処理機構１０の入口弁
１３および出口弁１４を開弁し、また放射線レベルが高
い場合には第３図に示す如くバイパスＭ９を閉ノ「し、
入［１升１３および出口弁Ｉ４をυｉｊ弁するように構
成されている。Then, when the pressure inside the reactor containment vessel 2 becomes equal to or higher than a certain set pressure, a passage 22 on this side a1+ turns the on-off valve 8 once, and furthermore, in this case, the radiation level inside the reactor containment vessel 2 is When the radiation level is low, the bypass valve 9 is opened as shown in FIG. 2, and the inlet valve 13 and outlet valve 14 of the radioactive materials disposal mechanism 10 are opened, and when the radiation level is high, the bypass valve 9 is opened as shown in FIG. Close bypass M9 as shown,
It is configured to control the inlet valve 13 and the outlet valve I4.
次にこの一実施例の作動を説明する。冷却材喪失事故が
生じ、原子炉枯納谷器２内に、４７＋温高圧の蒸気が砒
洩′Ｊ−るとこの蒸気は圧力抑制室（１小せず） ｌ／
Ｃ放出されて凝治１１シ、原子炉格納す器２内の圧力上
昇は防止される。また、このよ５７ｆ廂却利喪失川故時
には過熱されたジルコニウム合金製の燃料被覆室と冷却
（２との反応あるいは冷却伺の放射線分８￥、 ｋＬよ
って水素、峨素等の口」斧、（，１佳カスかう６生１゛
る用油性かある。そして、この１−ＩＪ燃性ガスは非凝
縮性であるため、圧力−＃’ｌｌ ＆１１イユでは凝Ｈ
されず、原子炉格納容器２内に蓄積されてゆく。そして
この原子炉格納容器２内の圧力がハ［雉の設定Ｌｆ以上
に上昇すると圧力検出器２０かもの信号により１１１］
伺ｊ回路２２から開ヅＰ信号が出力され、開閉弁８が開
弁する。Next, the operation of this embodiment will be explained. When a loss of coolant accident occurs and steam at a temperature of 47+ and high pressure leaks into the nuclear reactor Karanatani 2, this steam flows into the pressure suppression chamber (less than 1 liter).
C is released and cured, preventing a rise in pressure within the reactor containment vessel 2. In addition, at the time of the 57F accident, the overheated zirconium alloy fuel cladding chamber and cooling (reaction with 2 or cooling radiation amount of 8 yen, kL means hydrogen, dioxins, etc.) (There is an oil-based gas that can be used for 6 years and 1 months.) Since this 1-IJ combustible gas is non-condensable, at pressure -#'ll & 11
Instead, they accumulate in the reactor containment vessel 2. When the pressure inside the reactor containment vessel 2 rises above the setting Lf, a signal from the pressure detector 20 indicates 111.
An open/close signal is output from the open/close circuit 22, and the on-off valve 8 is opened.
そして、この場合に原子炉格納容器２内の放射・四レベ
ルが１．（（い場貧には第２図に示゛す如くバイパス弁
９が開弁し、放射性物置処理機構１０の入口３Ｐ１３お
よび出ロチ「１４は閉弁する。よって原子炉格納容器２
内の５Ｊ燃性ガスは開閉弁８、バイパス弁９を曲り、燃
焼機構１５で燃焼されたのち安全に外＠ｌｉ Ｋ放出さ
れる。なお、上記開閉ヅ［８を開弁するに先立って不活
性ガス注入機ｆｊｑ１７の注入井１９．１９を開弁じ・
不活性ガス供給源Ｉ８からこの放出管６内に窒素等の不
活性ガスを注入して空気をパージしておき、この放出管
６内で不活性ガスが燃焼しないようにする。また、原子
炉格納容器２内の放射線レベルが高い場合には第３図に
示す如くバイパス弁９が閉弁し、放射性拘留処理機構些
の入１］弁１３および出口弁１４が開弁される。したが
って、この原子炉格納容器２内のガスはボ／プＩ２によ
って放射性物質除去器ｌＩに送られ、含まれている放射
性物置が除去されたのち燃焼機構１５で燃焼されて安全
に外部に放出される。In this case, the radiation level inside the reactor containment vessel 2 is 1. ((In case of emergency, the bypass valve 9 is opened as shown in FIG.
The 5J combustible gas inside passes through the on-off valve 8 and the bypass valve 9, is burned in the combustion mechanism 15, and is then safely released to the outside. In addition, before opening the valve 8 above, open the injection well 19 and 19 of the inert gas injection machine fjq17.
An inert gas such as nitrogen is injected into the discharge pipe 6 from an inert gas supply source I8 to purge the air to prevent the inert gas from burning within the discharge pipe 6. Furthermore, when the radiation level inside the reactor containment vessel 2 is high, the bypass valve 9 is closed as shown in FIG. 3, and the radioactive detention processing mechanism inlet valve 13 and outlet valve 14 are opened. . Therefore, the gas in the reactor containment vessel 2 is sent to the radioactive material remover II by the bomb I2, and after the radioactive material contained therein is removed, it is burned in the combustion mechanism 15 and safely released to the outside. Ru.
したがって、原子炉格納容器２内の出力上列が防止され
る。また、この原子炉格納容器２内の５’Ｊ 燃性ガス
を放出することにより可燃性ガスの濃度が稀焼眠界以下
に抑えられ、この原子炉格納谷ン１警２内で可燃性ガス
が燃焼することか防止される。Therefore, a power overflow within the reactor containment vessel 2 is prevented. In addition, by releasing the 5'J flammable gas in this reactor containment vessel 2, the concentration of flammable gas is suppressed to below the rare burnout level, and the flammable gas is is prevented from burning.
なお、第４図には冷却材喪失事故が生じた場合の原子炉
陪納谷器２１りの出力上昇を解析した結氷を小１−０￥
なわち、事故後冷却材蒸気の漏出によって原子炉格納容
器２内の圧力は一時的に上＋１．−Ｊ−るが、この蒸気
は圧力抑制室に送られて凝縮し、圧力は低重する。次に
冷却祠とジルコニウムθ址練の燃相被抄管との反応ある
いは冷却伺の放射載分解によって水素、酸素等のり燃釣
、ノＪスが発止し、このｉ］燃性ガスは原子炉格納容器
２内に蓄積されてゆ＜、したがって従来のものは第４図
に破線で示ず如くこのＯ」燃性ガスの蓄積によって原子
炉格納容器内の圧力が急上昇するか、この一実施例のも
のは可燃性ガスが分縮Ｓ ｌ／Ｃ放出されるので１４図
に実線でボず如く原子炉４ｖ３納谷器内のＬＩ−力は低
下−してゆく。In addition, Figure 4 shows the ice formation, which is an analysis of the increase in the output of the reactor tank 21 in the event of a loss of coolant accident.
That is, due to the leakage of coolant vapor after the accident, the pressure inside the reactor containment vessel 2 temporarily rose to +1. However, this steam is sent to the pressure suppression chamber where it condenses and the pressure becomes low. Next, hydrogen, oxygen, etc. are generated by the reaction between the cooling chamber and the combustible phase tube of the zirconium Therefore, in the conventional system, as shown by the broken line in Fig. 4, the pressure inside the reactor containment vessel will rise rapidly due to the accumulation of flammable gas. In the example, combustible gas is released through partial condensation S1/C, so the LI power inside the reactor 4v3 reactor decreases as shown by the solid line in Fig. 14.
上述のｔｌＩＪ ＜本発明ｋｌ、一端が原子炉格納容器
内に連通し他９１にが外気に開放された放出管を設け、
この放出管の途中には開閉弁を設け、また放出管の他端
部にはこの放出管から放出される可燃性ガスを燃焼させ
る燃焼機構を設けたものである。したがって、原子炉格
納容器内に可燃性ガスが蓄積した場合にはこの開閉弁を
−弁じ、この原子炉格納容器２内のｎ■燃性ガスを燃焼
機ｈ４で燃焼させて安全に外部に放出し、原子炉格納容
器内の圧力上昇を防止するとともに可燃性ガスの譲曵を
燃焼眼界り下′に抑制して原子炉格納容器内部でρノ内
燃１／ｊ−ガスの燃焼を防止することができる等、その
効果は犬である。The above-mentioned tlIJ <the present invention kl, a discharge pipe is provided with one end communicating with the inside of the reactor containment vessel and the other end 91 open to the outside air,
An on-off valve is provided in the middle of the discharge pipe, and a combustion mechanism is provided at the other end of the discharge pipe to burn the combustible gas discharged from the discharge pipe. Therefore, if flammable gas accumulates in the reactor containment vessel, this on-off valve is turned off, and the flammable gas in the reactor containment vessel 2 is burned in the combustor h4 and safely released to the outside. To prevent the pressure increase in the reactor containment vessel and to suppress the yield of flammable gas to below the combustion limit, thereby preventing the combustion of ρ internal combustion 1/j-gas inside the reactor containment vessel. The effect is a dog.
図は本発明の一実施し１」を示し、第１図は概略構成図
、にｐｙ ２図および第３図は作動を説明するに帖構成
図、第４図はめ故後の原子炉格納容器内の圧力上ケ１の
ｇＩ析結釆を示す線図である。
２・・・原子炉鉱禾円谷器、３・・・原子炉圧力容器、
６・・・放出管、７・・・スタツク、８・・・開閉弁、
Ｌ」・・・放射性物η°処理機描、Ｉ５・・燃焼叡桁、
２０・・・＋ｉ＜力（火出器、２１・・放射糾恢出器、
２２・・・制御Ｌ！回路。The figure shows one embodiment of the present invention, Figure 1 is a schematic configuration diagram, Figures 2 and 3 are configuration diagrams for explaining the operation, and Figure 4 is a nuclear reactor containment vessel after a failure. FIG. 1 is a diagram showing gI precipitation at a pressure of 2... Nuclear reactor mine Tsuburayaki, 3... Nuclear reactor pressure vessel,
6...Discharge pipe, 7...Stack, 8...Opening/closing valve,
L”...Drawing of radioactive substance η° processing machine, I5...Combustion digit,
20...+i<force (fire extinguisher, 21...radiation condenser,
22...Control L! circuit.
Claims (2)
気中に開放された放出管と、この放出管の途中に設けら
れた開閉弁と、上り己放出管の他焔昔１５に設りられた
この放出管内から放出されるｔ５Ｊ燃性ノＪスを燃焼さ
セる燃焼機構とを貝伽したことを箱醍とする原子炉格納
容器内減圧装置紅。(1) A discharge pipe with one end communicating with the reactor containment vessel and the other end open to the atmosphere, an on-off valve installed in the middle of this discharge pipe, an upstream self-discharge pipe, and other parts. The main feature of this system is that it has a combustion mechanism that burns the t5J flammable gas released from the inside of the discharge pipe installed in the reactor containment vessel.
ていることを％徴と１′る一１１記材許珀氷θ〕範囲第
１項Ｓ己載の原子炉格納容器内減圧装置０(2) It is assumed that the other four dischargers have an opening in the upper box of the stack. Internal pressure reducing device 0
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57141941A JPS5931497A (en) | 1982-08-16 | 1982-08-16 | Depressing device for inside of reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57141941A JPS5931497A (en) | 1982-08-16 | 1982-08-16 | Depressing device for inside of reactor container |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5931497A true JPS5931497A (en) | 1984-02-20 |
| JPH0376439B2 JPH0376439B2 (en) | 1991-12-05 |
Family
ID=15303694
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57141941A Granted JPS5931497A (en) | 1982-08-16 | 1982-08-16 | Depressing device for inside of reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5931497A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2000019449A3 (en) * | 1998-09-30 | 2000-10-26 | Siemens Ag | Device and method for recombining hydrogen and oxygen in a gaseous mixture |
| JP2009529129A (en) * | 2006-03-07 | 2009-08-13 | アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング | Nuclear equipment and closure device in its containment vessel |
| JP2012225823A (en) * | 2011-04-21 | 2012-11-15 | Shimizu Corp | Method and equipment for preventing hydrogen explosion in nuclear power facility |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4836095A (en) * | 1971-09-09 | 1973-05-28 | ||
| JPS56128495A (en) * | 1980-03-14 | 1981-10-07 | Hitachi Ltd | Hydrogen processing system of nuclear reactor plant |
-
1982
- 1982-08-16 JP JP57141941A patent/JPS5931497A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4836095A (en) * | 1971-09-09 | 1973-05-28 | ||
| JPS56128495A (en) * | 1980-03-14 | 1981-10-07 | Hitachi Ltd | Hydrogen processing system of nuclear reactor plant |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2000019449A3 (en) * | 1998-09-30 | 2000-10-26 | Siemens Ag | Device and method for recombining hydrogen and oxygen in a gaseous mixture |
| KR100453794B1 (en) * | 1998-09-30 | 2004-10-20 | 프라마톰 아엔페 게엠베하 | Device and method for recombining hydrogen and oxygen in a gaseous mixture |
| JP2009529129A (en) * | 2006-03-07 | 2009-08-13 | アレヴァ エンペー ゲゼルシャフト ミット ベシュレンクテル ハフツング | Nuclear equipment and closure device in its containment vessel |
| US8126107B2 (en) | 2006-03-07 | 2012-02-28 | Areva Np Gmbh | Nuclear engineering plant and closure apparatus for its containment |
| US8509376B2 (en) | 2006-03-07 | 2013-08-13 | Areva Gmbh | Nuclear engineering plant and closure apparatus for its containment |
| JP2012225823A (en) * | 2011-04-21 | 2012-11-15 | Shimizu Corp | Method and equipment for preventing hydrogen explosion in nuclear power facility |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0376439B2 (en) | 1991-12-05 |
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