JPS60107599A - Treating facility for emergency gas of nuclear power plant - Google Patents

Treating facility for emergency gas of nuclear power plant

Info

Publication number
JPS60107599A
JPS60107599A JP21402383A JP21402383A JPS60107599A JP S60107599 A JPS60107599 A JP S60107599A JP 21402383 A JP21402383 A JP 21402383A JP 21402383 A JP21402383 A JP 21402383A JP S60107599 A JPS60107599 A JP S60107599A
Authority
JP
Japan
Prior art keywords
air
reactor building
nuclear power
power plant
air volume
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
JP21402383A
Other languages
Japanese (ja)
Inventor
純一 森田
尚 相庭
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 Engineering Corp
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Engineering Corp
Toshiba Corp
Nippon Genshiryoku Jigyo KK
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 Engineering Corp, Toshiba Corp, Nippon Genshiryoku Jigyo KK, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Engineering Corp
Priority to JP21402383A priority Critical patent/JPS60107599A/en
Publication of JPS60107599A publication Critical patent/JPS60107599A/en
Pending legal-status Critical Current

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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〕 本発明は原子力発電所の非常用ガス処理設備に係り、特
に、系統風量を所要の設計風量に保持するようにした原
子力発電所の非常用ガス処理設備に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to emergency gas processing equipment for nuclear power plants, and in particular to emergency gas processing equipment for nuclear power plants that maintains system air volume at a required design air volume. Regarding processing equipment.

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

一般に原子力発電所の非常用ガス処理設備(SGTS)
は原子炉事故等が発生した場合に、原子炉建屋の通常の
換気空調系から切替えられて自動起動し、原子炉建屋内
を負圧に保って原子炉格納容器よシ漏洩した核分裂生成
物の周囲への拡散を防止し、同時に高性能フィルタによ
シ放射性物質を取シ除いてスタックよシ外部へ放出する
ものである。
Generally, emergency gas treatment equipment (SGTS) in nuclear power plants
In the event of a nuclear reactor accident, the system automatically switches over from the reactor building's normal ventilation and air conditioning system, maintains negative pressure inside the reactor building, and removes fission products that have leaked out of the reactor containment vessel. This prevents the radioactive materials from dispersing into the surrounding environment, and at the same time removes the radioactive materials using a high-performance filter and releases them to the outside of the stack.

従来の原子力発電所の非常用ガス処理系は第1図に示す
ように構成され、二次格納施設である原子炉建屋1に換
気空調系2と共に非常用ガス処理設備3を備えている。
A conventional emergency gas treatment system for a nuclear power plant is constructed as shown in FIG. 1, and includes a ventilation air conditioning system 2 and emergency gas treatment equipment 3 in a reactor building 1, which is a secondary containment facility.

換気空調系2は原子炉建屋1内に外気を導入する給気ダ
ク)2aと、原子炉建屋l内の空気を外気へ放出する排
気ダク)2bとを有し、給気ダク)2aと排気ダク)2
bは原子炉建屋1内において給気ヘッダ2c、排気ヘラ
/2dにそれぞれ接続されると共に、原子炉建屋1外に
おいて隔離弁4,5をそれぞれ介装している。隔離弁5
の上流側の排気ダク)2bには非常用ガス処理設備3の
非常用排気ダクト6が接続され、図示しない原子炉格納
容器に事故が発生した場合は換気空調系2の隔離弁4,
5が共に緊急に閉弁し、換気空調系2による原子炉建屋
1内の換気は停止される。これとほぼ同時に非常用ガス
処理設備3のファン7が起動し、原子炉建屋1内の空気
は非常用排気ダクト6に案内されてフィルタによシ放射
性物質を除去され、図示しないスタックよシ外気へ放出
されるようになっている。
The ventilation air conditioning system 2 has an air supply duct) 2a that introduces outside air into the reactor building 1, and an exhaust duct) 2b that releases the air inside the reactor building 1 to the outside air. daku) 2
b is connected to an air supply header 2c and an exhaust header/2d inside the reactor building 1, and is provided with isolation valves 4 and 5 outside the reactor building 1, respectively. isolation valve 5
The emergency exhaust duct 6 of the emergency gas processing equipment 3 is connected to the upstream exhaust duct 2b of the reactor containment vessel (not shown), and the isolation valve 4 of the ventilation air conditioning system 2,
5 are both urgently closed, and ventilation in the reactor building 1 by the ventilation air conditioning system 2 is stopped. At almost the same time, the fan 7 of the emergency gas processing equipment 3 starts, and the air inside the reactor building 1 is guided to the emergency exhaust duct 6, where radioactive substances are removed by a filter, and the outside air is passed through the stack (not shown). It is designed to be released to

また、このような従来の非常用ガス処理設備3では、そ
の系統風量は原子炉建屋1内の自由空間容積を1日1回
処理できる風量に設計されている。
Further, in such conventional emergency gas processing equipment 3, the system air volume is designed to be such that the free space volume within the reactor building 1 can be treated once a day.

しかし、最近の原子力発電プラントでは原子炉建屋1等
を構成するコンクリートが気密度で良好なものとなった
こと、また、原子炉建屋1等の貫通部における気密処理
が向上したこと等にょp1原子炉建屋lの気密度が改善
された。このために、最近の原子力発電プラントでは非
常用ガス処理設備の系統風量が上記設計風量を100%
とすると、例えば30〜50%程度に減少した。この系
統風量の減少に伴ない原子炉格納容器(図示省略)等の
事故時の放出風量も減少したが、その反面、次のような
問題点を生するようになった。すなわち、原子炉建屋1
内の負圧厩が設計値よシも高くなシ、原子炉建屋10強
度上に問題が生じてきた。また、非常用排気ダクト6に
案内された排気ガスは外気放出前に電気ヒータにて加熱
されるが、系統風量が減少したために系統内温度が設計
温度を超えて高くなるという問題点があった。
However, in recent nuclear power plants, the concrete that makes up the reactor building 1, etc. has become better airtight, and the airtightness of the penetration parts of the reactor building 1, etc. has improved. The airtightness of the furnace building has been improved. For this reason, in recent nuclear power plants, the system air volume of emergency gas processing equipment is 100% of the above design air volume.
For example, it decreased to about 30 to 50%. Along with this reduction in system air volume, the amount of air released in the event of an accident from the reactor containment vessel (not shown) has also been reduced, but on the other hand, the following problems have arisen. That is, reactor building 1
Problems have arisen with regard to the strength of the reactor building, as the negative pressure inside the reactor building is higher than the design value. In addition, the exhaust gas guided to the emergency exhaust duct 6 is heated by an electric heater before being released to the outside air, but there was a problem in that the temperature inside the system became higher than the design temperature because the system air volume decreased. .

〔発明の目的〕[Purpose of the invention]

本発明は上述した事情に鑑みなされたもので、原子炉事
故発生時には系統風量がほぼ設計風量を保持するように
原子炉建屋内に外気を導入してこの原子炉建屋内の負圧
度を所要の設計値に保持すると共に、系統内温度の上昇
を抑制する原子力発電所内の非常用ガス処理設備を提供
することを目的とする。
The present invention was developed in view of the above-mentioned circumstances, and it is necessary to introduce outside air into the reactor building to maintain the necessary negative pressure in the reactor building so that the system air volume maintains approximately the design air volume in the event of a nuclear accident. The purpose of the present invention is to provide emergency gas processing equipment in a nuclear power plant that maintains the temperature at the design value and suppresses the rise in temperature within the system.

〔発明の概要〕[Summary of the invention]

上述した目的を達成するために本発明に係る原子力発電
所の非常用ガス処理設備は、次のように構成される。
In order to achieve the above-mentioned object, the emergency gas treatment equipment for a nuclear power plant according to the present invention is configured as follows.

原子炉事故発生時に原子炉部屋内雰囲気を換気空調する
換気空調系から切替えられてこの原子炉建屋内を所要の
負圧に保持する原子力発電所の非常用ガス処理設備にお
いて、原子炉事故発生時に上記原子炉建屋内に給気を導
入する給気配管を設け、系統風量がほぼ設計風量を保持
するように上記給気配管よシ給気を原子炉建屋内に導入
するように構成される。
In the emergency gas processing equipment of a nuclear power plant, which maintains the required negative pressure inside the reactor building by switching from the ventilation air conditioning system that ventilates and air-conditions the atmosphere inside the reactor room in the event of a reactor accident, An air supply pipe for introducing supply air into the reactor building is provided, and the air supply pipe is configured to introduce the supply air into the reactor building so that the system air volume maintains approximately the design air volume.

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

以下本発明の実施例を第2図および第3図に基づいて説
明する。
Embodiments of the present invention will be described below with reference to FIGS. 2 and 3.

第2図は本発明に係る原子力発電所の非常用ガス処理設
備の一実施例を示す系統図であシ、原子炉(図示省略)
の通常運転時に原子炉建屋1内の雰囲気を換気空調する
換気空調系2と、原子炉事故発生時にこの換気空調系2
から切替わって自動起動する非常用ガス処理設備10と
を示している。
FIG. 2 is a system diagram showing an embodiment of the emergency gas treatment equipment for a nuclear power plant according to the present invention, including a nuclear reactor (not shown).
A ventilation air-conditioning system 2 that ventilates and air-conditions the atmosphere inside the reactor building 1 during normal operation, and a ventilation air-conditioning system 2 that ventilates and air-conditions the atmosphere inside the reactor building 1 during normal operation.
The emergency gas processing equipment 10 is automatically started by switching from the above.

換気空調系2は原子炉建屋1内に外気を導入する給気ダ
クト2aと、原子炉建屋1内の空気を外気へ排出する排
気ダク) 2 b 、!:t=有する。給気ダクト2a
および排気ダクト2bは原子炉建屋1内において給気へ
ラダ2c、排気ヘッダ2dにそれぞれ接続され、この給
気ヘッダ2cおよび排気ヘッダ2dの分岐管の先端開口
部は原子炉建屋1の所要箇所に開口して給気ダク)2a
によシ案内され+ 西’3 fz jiff 2++5
 ハH会1「力FiG li ’&< a: Iff 
at i 、+ 7 −÷ここよシ取シ込んだ原子炉建
屋1内の空気を排気ダク)2bへ排出するようになって
いる。排気ダクト2bへ排出された排気ガスは適宜ガス
処理されて放射性物質を除去されてから図示しないスタ
ックよシ外気へ放出されるようになっている。
The ventilation air conditioning system 2 includes an air supply duct 2a that introduces outside air into the reactor building 1, and an exhaust duct that exhausts the air inside the reactor building 1 to the outside air. :t=has. Air supply duct 2a
The exhaust duct 2b is connected to a supply air ladder 2c and an exhaust header 2d in the reactor building 1, and the tip openings of the branch pipes of the supply air header 2c and the exhaust header 2d are located at required locations in the reactor building 1. Open air supply duct) 2a
Guided by + West '3 fz jiff 2++5
H-Kai 1 "Power FiG li '&< a: Iff
at i , + 7 - ÷ The air inside the reactor building 1 that has been sucked in here is discharged to the exhaust duct 2b. The exhaust gas discharged into the exhaust duct 2b is appropriately gas-treated to remove radioactive substances, and then is discharged into the outside air through a stack (not shown).

上記給気ダクト2aおよび排気ダクト2bには隔離弁4
,5がそれぞれ介装され、給気ダクト2aには隔離弁4
をパイ/eスするパイAス給気管1工が接続され、この
バイパス給気管11に風量調整弁12が介装される。一
方排気ダクト2bには隔離弁5の上流側で非常用排気ダ
クト13の一端が接続され、この排気ダクト1iの他端
は図示しないスタックに接続され、その中途は加熱ヒー
タ14およびフィルタ15を備えたトレイン16と排気
ファン17とを直列に接続したものを互いに並列に接続
して介装している。
Isolation valves 4 are provided in the air supply duct 2a and exhaust duct 2b.
, 5 are interposed respectively, and an isolation valve 4 is installed in the air supply duct 2a.
A bypass air supply pipe 1 is connected to the bypass air supply pipe 11, and an air volume adjustment valve 12 is interposed in the bypass air supply pipe 11. On the other hand, one end of an emergency exhaust duct 13 is connected to the exhaust duct 2b on the upstream side of the isolation valve 5, and the other end of this exhaust duct 1i is connected to a stack (not shown), which is equipped with a heater 14 and a filter 15 in the middle. A train 16 and an exhaust fan 17 are connected in series and connected in parallel to each other.

しかして、今ここで原子炉事故が発生した場合は換気空
調系2の給、排気側ダクト2a、2bの両隔離弁4,5
が共に緊急閉弁され、原子炉建屋1内の空気は閉じζめ
られる。これとハホ同時に非常用ガス処理設備10の所
要数の排気ファン17が起動し、原子炉建屋1内の空気
は非常用排気ダクト13へ排気され、所要数のトレイン
16に案内される。ここで排気ガスは加熱ヒータ14に
て加熱されると共に、フィルタ15にて放射性物質が除
去され、この後スタックよシ外気へ放出される。このた
めに原子炉建屋1内は負圧となる。はぼ同時にパイ・ぞ
ス給気管11の風量調整弁12が開弁され、このバイパ
ス給気管11を介して換気空調系2よシ原子炉建屋1内
に空気が導入される。この導入風量は、非常用ガス処理
設備10における系統風量が設計風量になるように設定
され、風量調整弁12の開度がIAI整される。したが
って原子炉建屋1の現実の気密匿が、例えば30 % 
/ 日の場合は、70%/日の風量をバイパス給気管1
1を介して原子炉建屋1内に導入するように風量調整弁
12の開度が調整される。
Therefore, if a nuclear reactor accident occurs now, both the isolation valves 4 and 5 of the supply and exhaust side ducts 2a and 2b of the ventilation air conditioning system 2
Both valves are emergency closed, and the air inside the reactor building 1 is closed. At the same time, the required number of exhaust fans 17 of the emergency gas processing equipment 10 are activated, and the air in the reactor building 1 is exhausted to the emergency exhaust duct 13 and guided to the required number of trains 16. Here, the exhaust gas is heated by the heater 14, radioactive substances are removed by the filter 15, and then released through the stack to the outside air. For this reason, the inside of the reactor building 1 becomes negative pressure. At about the same time, the air volume adjustment valve 12 of the pi-zos air supply pipe 11 is opened, and air is introduced into the reactor building 1 through the ventilation air conditioning system 2 through the bypass air supply pipe 11. The introduced air volume is set so that the system air volume in the emergency gas processing equipment 10 becomes the design air volume, and the opening degree of the air volume adjustment valve 12 is adjusted to IAI. Therefore, the actual airtightness of reactor building 1 is, for example, 30%.
/ day, 70%/day air volume bypass air supply pipe 1
The opening degree of the air volume adjustment valve 12 is adjusted so that the air is introduced into the reactor building 1 through the air flow control valve 12.

すなわち、導入風量は非常用ガス処理設備10における
設削風量と原子炉建屋1の現実の気密度との差分に設定
され、系統風量が常に設計風量になるように風量調整弁
12の開度が調整される。これによシ系統風量が一定と
なシ、加熱ヒータ14が一定温度で排気ガスを加温して
も系統内温塵が設計温度を越えるような事態が回避され
る。しだがって、系統風量に応じて加熱ヒータ14の加
温温度を制御する必要がない。非常用ガス処理設備1o
の系統風量が設計風量に保持される結果、原子炉建屋1
内の負圧度も設計値の例えば−6,4■Aqに維持され
、原子炉建屋10過負圧に伴なう強度上の問題点も解消
される。
That is, the introduced air volume is set to the difference between the designed air volume in the emergency gas processing equipment 10 and the actual air tightness of the reactor building 1, and the opening degree of the air volume adjustment valve 12 is set so that the system air volume always becomes the design air volume. be adjusted. As a result, even if the system air volume remains constant and the heater 14 heats the exhaust gas at a constant temperature, a situation in which the heated dust in the system exceeds the design temperature is avoided. Therefore, there is no need to control the heating temperature of the heater 14 according to the system air volume. Emergency gas processing equipment 1o
As a result, the system air volume of reactor building 1 is maintained at the design air volume.
The degree of negative pressure inside the nuclear reactor building 10 is also maintained at a design value of, for example, -6.4 ■Aq, and the strength problems associated with excessive negative pressure in the reactor building 10 are also resolved.

第3図は本発明の他の実施例による非常用ガス処理設備
の系統図であり、本実施例は外気を原子炉建屋1内へ導
入する非常用給気ダク)20を設けている。この非常用
給気ダク)20は換気空調系2よシ原子炉建屋1内へ給
気するようにした第2図で示す実施例とは異なり、換気
空調系2以外の、例えば外気を直接この原子炉建屋1内
へ導入するようになっている。非常用給気ダク)20は
風量調整弁21を介装しておシ、この風量調整弁21は
上述した実施例の場合と同様に開度調整される。すなわ
ち、非常用処理ガス設備10における系統風量が設計風
量を保持するように風量調整弁21の開度が調整される
FIG. 3 is a system diagram of an emergency gas processing facility according to another embodiment of the present invention, and this embodiment is provided with an emergency air supply duct 20 for introducing outside air into the reactor building 1. This emergency air supply duct) 20 is different from the embodiment shown in FIG. 2 in which air is supplied from the ventilation air conditioning system 2 into the reactor building 1. It is designed to be introduced into the reactor building 1. The emergency air supply duct) 20 is provided with an air volume adjustment valve 21, and the opening degree of this air volume adjustment valve 21 is adjusted in the same manner as in the above-described embodiment. That is, the opening degree of the air volume adjustment valve 21 is adjusted so that the system air volume in the emergency processing gas facility 10 maintains the designed air volume.

なお、第3図中、第2図と同一部材には同一符号を付し
てその説明を省略している。
In FIG. 3, the same members as those in FIG. 2 are given the same reference numerals and their explanations are omitted.

〔発明の効果〕〔Effect of the invention〕

以上説明したように本発明に係る原子力発電所の非常用
ガス処理設備は、その系統風量が設計風量を保持するよ
うに給気を原子炉建屋内に導入する給気配管を設けたの
で、原子炉建屋内の負圧度ははは設計値に保持され、過
負圧に伴う原子炉建屋の強度上の問題は解消され、また
、非常用ガス処理設備の系統風量が設計風量に常に一定
に保持されるために、この系統へ排出される排気ガスを
加温する加熱ヒータの加温温度が一定であっても、この
系統の系統内温塵が設計温度を越えるような事態も未然
に防止される。また、上記ヒータの加温温度を系統風量
の多少に応じて制御する必要も無くなシ、系統の簡素化
を図ることができる。
As explained above, the emergency gas processing equipment for a nuclear power plant according to the present invention is equipped with air supply piping that introduces air into the reactor building so that the system air volume maintains the design air volume, so that the The degree of negative pressure inside the reactor building is maintained at the design value, problems with the strength of the reactor building due to excessive negative pressure are resolved, and the system air volume of the emergency gas processing equipment is always kept constant at the design air volume. Even if the heating temperature of the heater that heats the exhaust gas discharged into this system remains constant, it prevents the situation in which the temperature of the dust inside this system exceeds the design temperature. be done. Furthermore, there is no need to control the heating temperature of the heater according to the system air volume, and the system can be simplified.

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

第1図は従来の原子力発電所の非常用ガス処理設備の系
統図、第2図は本発明に係る原子力発電所の非常用ガス
処理設備の一実施例の系統図、第3図は本発明に係る原
子力発電所の非常用ガス処理設備の他の実施例の系統図
である。 1・・・原子炉建屋、2・・・換気空調系、2a・・・
給気ダクト、2b・・・排気ダクト、2C・・・給気ヘ
ッダ、2d・・・排気ヘッダ、3.10・・・非常用ガ
ス処理系、4.5・・・隔離弁、6.13・・・非常用
排気ダクト、7.17・・・排気ファン、11・・・バ
イパス給気管、12 、21・・・風量調整弁、14・
・・加熱ヒータ、15・・・フィルタ、16・・・トレ
イン。 出願人代理人 波 多 野 久
Fig. 1 is a system diagram of a conventional emergency gas processing equipment for a nuclear power plant, Fig. 2 is a system diagram of an embodiment of an emergency gas processing equipment for a nuclear power plant according to the present invention, and Fig. 3 is a system diagram of an embodiment of the emergency gas processing equipment for a nuclear power plant according to the present invention. FIG. 2 is a system diagram of another embodiment of the emergency gas processing equipment for a nuclear power plant according to the present invention. 1... Reactor building, 2... Ventilation air conditioning system, 2a...
Supply air duct, 2b...Exhaust duct, 2C...Air supply header, 2d...Exhaust header, 3.10...Emergency gas treatment system, 4.5...Isolation valve, 6.13 ...Emergency exhaust duct, 7.17...Exhaust fan, 11...Bypass air supply pipe, 12, 21...Air volume adjustment valve, 14.
...heater, 15...filter, 16...train. Applicant's agent Hisashi Hatano

Claims (1)

【特許請求の範囲】 1、原子炉事故発生時に原子戸建屋内雰囲気を換気空調
する換気空調系から切替えられてこの原子炉建屋内を所
要の負圧に保持する原子力発電所の非常用ガス処理設備
において、原子炉事故発生時に上記原子炉建屋内に給気
を導入する給気配管を設け、系統風量がほぼ設計風量を
保持するように上記給気配管ニジ給気を原子炉建屋内に
導入するようにしたことを特徴とする原子力発電所の非
常用ガス処理設備。 2、給気配管は、原子炉建屋の換気空調系の給気ダクト
に介装した隔離弁をパイノぐスするバイパスラインと、
このパイパスラインに介装され導入風量を調整する風量
調整弁とを有する特許請求の範囲第1項に記載の原子力
発電所の非常用ガス処理設備。 3、給気配管は、原子炉建屋内に直接外気を導入する給
気配管と、この給気配管に介装され導入風量を調整する
風量調整弁とを有する特許請求の範囲第1項に記載の原
子力発電所の非常用ガス処理設備。
[Scope of Claims] 1. Emergency gas processing for a nuclear power plant that maintains the reactor building at a required negative pressure by switching from the ventilation air conditioning system that ventilates and air-conditions the atmosphere inside the nuclear building when a nuclear reactor accident occurs. In the equipment, air supply piping is installed to introduce supply air into the reactor building in the event of a reactor accident, and supply air is introduced into the reactor building through the air supply piping so that the system air volume maintains approximately the design air volume. Emergency gas processing equipment for a nuclear power plant, characterized in that it is configured to: 2. The air supply piping is a bypass line that connects the isolation valve installed in the air supply duct of the ventilation air conditioning system of the reactor building.
The emergency gas processing equipment for a nuclear power plant according to claim 1, further comprising an air volume adjustment valve that is installed in the bypass line and adjusts the amount of air introduced. 3. The air supply piping includes an air supply pipe that directly introduces outside air into the reactor building, and an air volume adjustment valve that is interposed in the air supply pipe and adjusts the introduced air volume. emergency gas treatment equipment at a nuclear power plant.
JP21402383A 1983-11-16 1983-11-16 Treating facility for emergency gas of nuclear power plant Pending JPS60107599A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP21402383A JPS60107599A (en) 1983-11-16 1983-11-16 Treating facility for emergency gas of nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP21402383A JPS60107599A (en) 1983-11-16 1983-11-16 Treating facility for emergency gas of nuclear power plant

Publications (1)

Publication Number Publication Date
JPS60107599A true JPS60107599A (en) 1985-06-13

Family

ID=16648991

Family Applications (1)

Application Number Title Priority Date Filing Date
JP21402383A Pending JPS60107599A (en) 1983-11-16 1983-11-16 Treating facility for emergency gas of nuclear power plant

Country Status (1)

Country Link
JP (1) JPS60107599A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20130126508A1 (en) * 2011-11-17 2013-05-23 Texas Instruments Incorporated Extending Radiation Tolerance By Localized Temperature Annealing Of Semiconductor Devices

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58105098A (en) * 1981-12-18 1983-06-22 株式会社日立製作所 Radioactive gas processing device

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58105098A (en) * 1981-12-18 1983-06-22 株式会社日立製作所 Radioactive gas processing device

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20130126508A1 (en) * 2011-11-17 2013-05-23 Texas Instruments Incorporated Extending Radiation Tolerance By Localized Temperature Annealing Of Semiconductor Devices

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