JPS6249958B2 - - Google Patents
Info
- Publication number
- JPS6249958B2 JPS6249958B2 JP56056827A JP5682781A JPS6249958B2 JP S6249958 B2 JPS6249958 B2 JP S6249958B2 JP 56056827 A JP56056827 A JP 56056827A JP 5682781 A JP5682781 A JP 5682781A JP S6249958 B2 JPS6249958 B2 JP S6249958B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor building
- exhaust
- flow rate
- gas treatment
- emergency gas
- 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.)
- Expired
Links
- 238000002955 isolation Methods 0.000 claims description 24
- 238000001514 detection method Methods 0.000 claims description 3
- 238000012360 testing method Methods 0.000 description 11
- 230000002159 abnormal effect Effects 0.000 description 4
- 230000000737 periodic effect Effects 0.000 description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 238000013021 overheating Methods 0.000 description 2
- 230000002265 prevention Effects 0.000 description 2
- 230000001629 suppression Effects 0.000 description 2
- 230000003213 activating effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000011056 performance test Methods 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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)
Description
【発明の詳細な説明】
本発明は、原子力発電プラントにおける原子炉
建屋の非常ガス処理装置に係り、この原子炉建屋
の非常ガス処理装置による原子炉建屋の異常負圧
防止装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an emergency gas treatment device for a reactor building in a nuclear power plant, and more particularly to an abnormal negative pressure prevention device for the reactor building using the emergency gas treatment device for the reactor building.
一般に、原子炉建屋内は、非常ガス発生による
屋外への拡散防止を図る安全性の見地から、負圧
状態に保持されている。 Generally, the inside of a nuclear reactor building is maintained at a negative pressure state from a safety standpoint to prevent emergency gas generation from spreading outside.
又一方、原子力発電プラントにおける原子炉建
屋の非常ガス処理装置による異常負圧防止装置
は、全く提案されていないため、安全信号として
の原子炉建屋隔離を検出して発信する検出器が、
例えば、(1)原子炉(圧力容器)水位低下(L―
3)、(2)格納容器の圧力高、(3)原子炉建屋の放射
能高、又は、(4)燃料交換床の放射能高等のいずれ
か一つの異常現象を検出すると、予め、原子炉建
屋内に設置された(a)非常ガス処理系が自動的に起
動して、その排風機の入口流量制御弁の開度で設
定値まで流量を増加すると共に、(b)原子炉建屋の
通常換気系を停止する。(c)さらに、原子炉建屋を
給・排気ダクトから完全に隔離して上記非常ガス
処理系でその気密性に応じた負圧値まで減圧し
て、上記原子炉建屋から非常ガスの漏洩を防止す
るようになつている。 On the other hand, since no abnormal negative pressure prevention device using an emergency gas treatment device in the reactor building in a nuclear power plant has been proposed, the detector that detects and sends out the isolation of the reactor building as a safety signal is
For example, (1) Nuclear reactor (pressure vessel) water level drop (L-
3), (2) High pressure in the containment vessel, (3) High radioactivity in the reactor building, or (4) High radioactivity in the refueling floor. (a) The emergency gas treatment system installed in the reactor building automatically starts up and increases the flow rate to the set value depending on the opening of the inlet flow control valve of the exhaust fan, and (b) Shut down the ventilation system. (c)Furthermore, the reactor building is completely isolated from the supply and exhaust ducts, and the emergency gas treatment system is used to reduce the pressure to a negative pressure value appropriate to its airtightness, thereby preventing leakage of emergency gas from the reactor building. I'm starting to do that.
このように、気密性の良好な原子炉建屋内は、
外気に対して異常負圧になるため、上記非常ガス
処理系の排風機の流量を低減することを余儀なく
される。 In this way, inside the reactor building with good airtightness,
Since the pressure becomes abnormally negative with respect to the outside air, it is necessary to reduce the flow rate of the exhaust fan of the emergency gas treatment system.
しかしながら、上述した非常ガス処理系は、原
子炉建屋の減圧(負圧)によつて、排風機のサー
ジング現象やフイルタートレインに内蔵された加
熱ヒータによるトレイン内の過熱現象を生じる等
の不具合がある。又、上記トレイン内の過熱現象
を抑制するために、加熱用ヒータを手動に切換え
て停止すると、トレイン内の活性炭フイルタの湿
度が上昇する等の欠点がある。 However, the above-mentioned emergency gas treatment system has problems such as surging of the exhaust fan and overheating inside the train due to the heater built into the filter train due to the reduced pressure (negative pressure) in the reactor building. . Furthermore, if the heating heater is manually switched and stopped in order to suppress the overheating phenomenon in the train, there are drawbacks such as an increase in the humidity of the activated carbon filter in the train.
又一方、原子力発電プラントにおける定期検査
時に、上記非常ガス処理系を運転して、上記フイ
ルタートレインによるフイルターの性能試験を行
う場合、上記非常ガス処理系は、その吸入口とし
ての給気ダクトを原子炉建屋としているため、例
えば、原子炉建屋内の作業を中断して室内空気の
浄化を余儀なくされるばかりでなく、定期的に実
施される原子炉建屋漏洩試験時においては、巨大
な建屋内と大気(外気)との差圧を常時、一定に
保持することは困難であるから、漏洩試験実施ご
とに、流量、差圧の条件の下で、過去の漏洩試験
結果との比較を行い、原子炉建屋の気密状況が以
前とどのように変化しているかを検出することが
困難である。 On the other hand, when operating the emergency gas treatment system to perform a filter performance test using the filter train during periodic inspections in a nuclear power plant, the emergency gas treatment system may Because the reactor building is a reactor building, for example, not only is work inside the reactor building forced to be interrupted to purify the indoor air, but during periodic reactor building leak tests, the huge building It is difficult to maintain a constant pressure difference with the atmosphere (outside air) at all times, so each time a leak test is conducted, a comparison is made with past leak test results under the conditions of flow rate and pressure difference. It is difficult to detect how the airtightness of the furnace building has changed from before.
即ち、上記原子炉建屋の差圧条件の下では、原
子炉建屋の開閉扉の締付具合い、各種シール部の
リーク状態等が、前回の差圧条件のもとでその
まゝ再現することは困難である。 In other words, under the above differential pressure conditions in the reactor building, the tightness of the reactor building's opening/closing doors, the leakage conditions of various seals, etc. cannot be reproduced as they were under the previous differential pressure conditions. Have difficulty.
本発明は、上述した点に鑑み、原子炉建屋の非
常ガス処理系において、隔離弁と流量検出器との
間に位置する排気ダクトに給気チヤンバーの外気
取入れ管を接続し、この外気取入れ管に逆止ダン
パー及び流量コントロール弁を設け、この流量コ
ントロール弁に接続され、しかも、上記原子炉建
屋の差圧を検出して発信する差圧発信器を上記原
子炉建屋に設け、これにより、原子炉建屋の隔離
信号で上記非常ガス処理系が起動したとき、原子
炉建屋内の異常負圧を防止して原子炉建屋内と外
気とを一定の差圧値(負圧)に保持すると共に、
流量制限値を越えて流量低減による排風機のサー
ジング現象の発生を防止し、併せて、非常ガス処
理系の漏洩量を測定する単独運転試験ができるよ
うにしたことを目的とする非常ガス処理装置を提
供するものである。 In view of the above-mentioned points, the present invention connects an outside air intake pipe of an air supply chamber to an exhaust duct located between an isolation valve and a flow rate detector in an emergency gas treatment system of a nuclear reactor building. A check damper and a flow control valve are provided in the reactor building, and a differential pressure transmitter is provided in the reactor building that is connected to the flow control valve and detects and transmits the differential pressure in the reactor building. When the emergency gas treatment system is activated by a reactor building isolation signal, it prevents abnormal negative pressure within the reactor building and maintains a constant differential pressure value (negative pressure) between the reactor building and outside air.
An emergency gas treatment system that prevents the occurrence of surging in the exhaust fan due to a flow rate reduction that exceeds the flow rate limit value, and also enables standalone operation tests to measure the amount of leakage from the emergency gas treatment system. It provides:
以下、本発明を図示の一実施例について説明す
る。 Hereinafter, the present invention will be described with reference to an illustrated embodiment.
図において、符号1はコントロールの遮蔽体で
構築された原子炉建屋であつて、この原子炉建屋
1内には原子炉としての圧力容器2を内蔵した格
納容器(ドライウエル)3が設置されている。
又、上記原子炉建屋1の一側には外気ルーバ4a
を備えた給気チヤンバ4が、給気ダクト5を介し
て建屋内に連通するようにして設られており、こ
の給気ダクト5には独立して作動する各給気送風
機6a,6b及び各給気隔離弁7a,7bが設置
されている。さらに、上記原子炉建屋1内に引き
通された上記給気ダクト5には、上記格納容器3
に連通する調気系配管8の給気管8aが設けられ
ており、この給気管8aには各開閉弁9,10が
配設されている。さらに又、上記格納容器3の他
側には上記調気系配管8の排気管8bが接続され
ており、この排気管8bには各開閉弁11,12
及び隔離弁13を備えたバイパス(側路)14が
設置されている。 In the figure, reference numeral 1 is a reactor building constructed with a control shield, and inside this reactor building 1, a containment vessel (dry well) 3 containing a pressure vessel 2 as a nuclear reactor is installed. There is.
Also, on one side of the reactor building 1, there is an outside air louver 4a.
An air supply chamber 4 equipped with an air supply chamber 4 is provided so as to communicate with the inside of the building via an air supply duct 5. Supply air isolation valves 7a and 7b are installed. Further, the supply air duct 5 that is led into the reactor building 1 is provided with the containment vessel 3.
An air supply pipe 8a of the air control system piping 8 is provided, which communicates with the air control system piping 8, and each on-off valve 9, 10 is provided in this air supply pipe 8a. Furthermore, an exhaust pipe 8b of the air control system piping 8 is connected to the other side of the containment vessel 3, and each on-off valve 11, 12 is connected to the exhaust pipe 8b.
A bypass 14 with an isolation valve 13 is installed.
一方、上記給気管8aには上記格納容器3のサ
プレツシヨンチエンバー3aに接続された弁15
を有する枝管16が設けられており、上記排気管
8bには上記サプレツシヨンチエンバー3aに接
続された枝管19が開閉弁17及び隔離弁18を
備えたパイパス20によつて構成されている。 On the other hand, the air supply pipe 8a has a valve 15 connected to the suppression chamber 3a of the containment vessel 3.
A branch pipe 16 is provided in the exhaust pipe 8b, and a branch pipe 19 connected to the suppression chamber 3a is constituted by a bypass 20 equipped with an on-off valve 17 and an isolation valve 18. There is.
他方、上記原子炉建屋1の他側には主排気筒2
1が主排気ダクト22を介して建屋内に連通する
ようにして設けられており、この主排気ダクト2
2には各排気用隔離弁23、排気チヤンバー24
及び独立して作動する各開閉弁25a,25及び
各排気フアン26a,26bがそれぞれ設置され
ている。又、上記排気ダクト22の一部には上記
排気管8bが接続されており、この排気管8bに
は排気フアン27が設置されている。 On the other hand, there is a main exhaust stack 2 on the other side of the reactor building 1.
1 is provided so as to communicate with the inside of the building via a main exhaust duct 22, and this main exhaust duct 2
2 includes each exhaust isolation valve 23 and exhaust chamber 24.
Opening/closing valves 25a, 25 and exhaust fans 26a, 26b, which operate independently, are installed. Further, the exhaust pipe 8b is connected to a part of the exhaust duct 22, and an exhaust fan 27 is installed in the exhaust pipe 8b.
又一方、上記各排気用隔離弁23の上流側に位
置する上記主排気ダクト22には、非常ガス処理
系を構成する排気ダクト28が上記主排気筒2
1に連通するようにして並列にして設けられてお
り、上記主排気ダクト22に近接した位置の上記
排気ダクト28には切換弁29及び切換弁30を
備えたバイパス31が附設されている。さらに、
上記切換弁29の下流側に位置する上記排気ダク
ト28には切換弁32を備えた枝管33が上記排
気管8bに連通するようにして接続されている。
又、上記枝管33の接続した位置の上記排気ダク
ト28には流量計34が設けられており、この流
量計34は上記非常ガス処理系に流れるすべて
の流体の流量を計測し得るようになつている。さ
らに又、上記流量計34の下流側に位置して並列
に設けられた上記排気ダクト28には独立した各
隔離弁35a,35b、各流量検出器36a,3
6b、各フイルタートレイン37a,37b、各
流量制御弁38a,38b及び各排風機39a,
39bが順に設置されており、上記各フイルター
トレイン37a,37bと各流量制御弁38a,
38bとの間に位置する上記両排気ダクト28と
の間には開閉弁40を備えたバイパス41が設け
られている。 On the other hand, in the main exhaust duct 22 located upstream of each of the exhaust isolation valves 23, an exhaust duct 28 constituting an emergency gas treatment system is connected to the main exhaust pipe 22.
1, and a bypass 31 having a switching valve 29 and a switching valve 30 is attached to the exhaust duct 28 at a position close to the main exhaust duct 22. moreover,
A branch pipe 33 provided with a switching valve 32 is connected to the exhaust duct 28 located downstream of the switching valve 29 so as to communicate with the exhaust pipe 8b.
Further, a flow meter 34 is provided in the exhaust duct 28 at a position where the branch pipe 33 is connected, and this flow meter 34 can measure the flow rate of all fluids flowing into the emergency gas treatment system. ing. Furthermore, the exhaust duct 28, which is provided in parallel downstream of the flow meter 34, includes independent isolation valves 35a, 35b and flow rate detectors 36a, 3.
6b, each filter train 37a, 37b, each flow control valve 38a, 38b, and each exhaust fan 39a,
39b are installed in order, each filter train 37a, 37b and each flow control valve 38a,
A bypass 41 equipped with an on-off valve 40 is provided between the exhaust ducts 28 and the exhaust ducts 38b.
他方、上記各隔離弁35a,35bと各流量検
出器36a,36bとの間に位置する上記各排気
ダクト28には前記給気チヤンバー4の外気取入
れ管42が接続されており、この外気取入れ管4
2には逆止ダンパー(自動ダンパー)43及び電
磁石で作動する流量コントロール弁44が設置さ
れている。さらに、この流量コントロール弁44
には差圧発信器45が電気的に接続されており、
この差圧発信器45は前記原子炉建屋1の建屋内
圧と外気との圧力との差圧を検出し、この検出信
号によつて上記流量コントロール弁44を作動し
得るようになつている。即ち、この差圧発信器4
5は、原子炉建屋1内の圧力が大きく低減する
と、この原子炉建屋1内の基準負圧以下にならな
いように、上記流量コントロール弁44を大きく
開弁して、外気を外気取入れ管42から非常ガス
処理系の各排気ダクト28へ供給するようにな
つている。 On the other hand, the outside air intake pipe 42 of the air supply chamber 4 is connected to each of the exhaust ducts 28 located between the isolation valves 35a, 35b and the flow rate detectors 36a, 36b. 4
2 is provided with a check damper (automatic damper) 43 and a flow control valve 44 operated by an electromagnet. Furthermore, this flow control valve 44
A differential pressure transmitter 45 is electrically connected to the
This differential pressure transmitter 45 detects the differential pressure between the internal pressure of the reactor building 1 and the pressure of outside air, and can operate the flow rate control valve 44 based on this detection signal. That is, this differential pressure transmitter 4
5, when the pressure inside the reactor building 1 is greatly reduced, the flow rate control valve 44 is opened wide to prevent the pressure inside the reactor building 1 from falling below the reference negative pressure, and outside air is drawn from the outside air intake pipe 42. The gas is supplied to each exhaust duct 28 of the emergency gas treatment system.
以下、本発明の作用について説明する。 Hereinafter, the effects of the present invention will be explained.
(1) 原子力発電プラントにおける通常運転時、
原子力発電プラントにおける通常運転時、一
方の給気送風機6a及び一方の排気フアン26
aが運転されると、同時に各給気隔離弁7a,
7b及び各排気用隔離弁23と開閉弁25aが
全開されている。他方、上記排気フアン27及
び非常ガス処理系は停止し、しかも各切換弁
29,30、各隔離弁35a,35b、各流量
制御弁38a,38b及び流量コントロール弁
44は閉弁状態におかれる。従つて、上記原子
炉建屋1内の空気の流れは、給気チヤンバー4
の外気ルーバ4aから外気を吸入して過し、
これを、上記給気ダクト5より原子炉建屋1内
に給気される。しかして、この原子炉建屋1内
の汚れた空気は、主排気ダクト22に設置され
た排気チヤンバー24で浄化して主排気筒21
から大気中に排棄される。(1) During normal operation in a nuclear power plant, during normal operation in a nuclear power plant, one supply air blower 6a and one exhaust fan 26
When a is operated, each supply air isolation valve 7a,
7b, each exhaust isolation valve 23, and the on-off valve 25a are fully opened. On the other hand, the exhaust fan 27 and the emergency gas treatment system are stopped, and the switching valves 29 and 30, the isolation valves 35a and 35b, the flow control valves 38a and 38b, and the flow control valve 44 are closed. Therefore, the air flow inside the reactor building 1 is controlled by the air supply chamber 4.
The outside air is sucked in from the outside air louver 4a,
This air is supplied into the reactor building 1 through the air supply duct 5. Therefore, the dirty air inside the reactor building 1 is purified by the exhaust chamber 24 installed in the main exhaust duct 22, and the air is purified by the exhaust chamber 24 installed in the main exhaust duct 22.
is emitted into the atmosphere.
(2) 原子炉建屋の隔離信号発生時、
原子炉建屋内に予め設置された検出器(図示
されず)が原子炉建屋1の隔離信号を発信し
て、この信号によつて上記非常ガス処理系の
各排風機39a,39bが運転を開始すると同
時に、上記各切換弁29,30、各隔離弁35
a,35b、各流量制御弁38a,38bは開
弁状態となり、上記給気送風機6a、排気フア
ン26aが停止し、同時に、各給気隔離弁7
a,7b及び各排気用隔離弁23、と開閉弁2
5aが閉弁する。(2) When a reactor building isolation signal is generated, a detector (not shown) installed in advance in the reactor building transmits an isolation signal for the reactor building 1, and this signal causes the above emergency gas treatment to be carried out. At the same time when the exhaust fans 39a and 39b of the system start operating, the switching valves 29 and 30 and the isolation valves 35
a, 35b, and each flow control valve 38a, 38b are opened, the supply air blower 6a and exhaust fan 26a are stopped, and at the same time, each supply air isolation valve 7 is opened.
a, 7b, each exhaust isolation valve 23, and on-off valve 2
5a closes.
従つて、上記原子炉建屋1内の空気の流れ
は、徐々に負圧状態に減圧されて、汚れた空気
は上記非常ガス処理系を通して上記主排気筒
21から大気中に排棄される。又、上記原子炉
建屋1内が基準負圧値に達すると、上記差圧発
信器45が作動し、この検出信号によつて、上
記流量コントロール弁44を開弁し、外気を外
気取入れ管42から上記非常ガス処理系の各
排気ダクト28へ供給し得るようになつてい
る。 Therefore, the air flow within the reactor building 1 is gradually reduced to a negative pressure state, and the contaminated air is discharged into the atmosphere from the main exhaust stack 21 through the emergency gas treatment system. Further, when the inside of the reactor building 1 reaches the reference negative pressure value, the differential pressure transmitter 45 is activated, and this detection signal opens the flow rate control valve 44 to direct outside air to the outside air intake pipe 42. The gas can be supplied from the gas to each exhaust duct 28 of the emergency gas treatment system.
(3) 非常ガス処理系のテスト運転時
非常ガス処理系のテスト運転をする場合に
は、予め、流量コントロール弁44、を手動に
よつて開弁し、上記各隔離弁35a,35bを
手動によつて閉弁し、他方、上記排気ダクト2
8の各排風機39a,39bを運転することに
よつて行われる。即ち、これによつて、上記各
流量制御弁38a,38bは定格流量開度まで
自動的に開弁するので、原子炉建屋1から独立
して非常ガス処理系のテスト運転をすること
ができる。(3) During test operation of the emergency gas treatment system When performing a test operation of the emergency gas treatment system, first manually open the flow rate control valve 44, and then manually open each of the isolation valves 35a and 35b. The valve is then closed, and on the other hand, the exhaust duct 2
This is done by operating the eight exhaust fans 39a and 39b. That is, as a result of this, each of the flow rate control valves 38a and 38b is automatically opened to the rated flow rate opening, so that a test operation of the emergency gas treatment system can be performed independently from the reactor building 1.
(4) 原子炉建屋の気密・漏洩の試験時(非常ガス
処理系使用)。(4) During airtightness/leakage testing of reactor building (emergency gas treatment system used).
原子炉建屋の気密、漏洩試験は、原子炉建屋
1を隔離する状態において、上記非常ガス処理
系を起動することにより行われる。即ち、上
記非常ガス処理系の吸込側は、主排気ダクト
22に連通している。又、上記流量コントロー
ル弁44は上記差圧発信器45によつて開閉制
御される。 The airtightness and leakage tests of the reactor building are performed by activating the emergency gas treatment system while the reactor building 1 is isolated. That is, the suction side of the emergency gas treatment system communicates with the main exhaust duct 22. Further, the opening and closing of the flow rate control valve 44 is controlled by the differential pressure transmitter 45.
このときの差圧を試験値として設定すれば、
このときの原子炉建屋1は非常ガス処理系に
おける流量計34によつて空気の漏洩量を検査
することができる。 If the differential pressure at this time is set as the test value,
At this time, the reactor building 1 can inspect the amount of air leakage using the flow meter 34 in the emergency gas treatment system.
なお、上述した空気漏洩量は、後の定期検査
時に経年変化に伴う原子炉建屋の気密状態を示
す目安にすることができる。 Note that the above-mentioned air leakage amount can be used as a guideline to indicate the airtightness of the reactor building due to secular changes during a later periodic inspection.
以上述べたように本発明によれば、原子炉建屋
1と主排気筒21との間に排気ダクト28を並列
に設け、この排気ダクト28に隔離弁35a,3
5b、流量検出器36a,36b、フイルタート
レイン37a,37b、流量制御弁38a,38
b及び排風機39a,39bを順に設置し、上記
隔離弁35a,35bと流量検出器36a,36
bとの間に位置する上記排気ダクト28に給気チ
ヤンバー4の外気取入れ管42を接続し、この外
気取入れ管42に逆止ダンパー43及び流量コン
トロール弁44を設け、この流量コントロール弁
44に接続され、しかも、上記原子炉建屋1の差
圧を検出して発信する差圧発信器45を上記原子
炉建屋1に設けてあるので、非常ガス処理系が
作動した時、原子炉建屋1内を異常負圧を防止で
きるばかりでなく、排風機39a,39bのサー
ジング現象を防止し、併せて、非常ガス処理系
を独立してテスト運転することもできる等の効果
を有するものである。 As described above, according to the present invention, the exhaust duct 28 is provided in parallel between the reactor building 1 and the main exhaust stack 21, and the isolation valves 35a, 3
5b, flow rate detectors 36a, 36b, filter trains 37a, 37b, flow rate control valves 38a, 38
b and exhaust fans 39a, 39b are installed in order, and the isolation valves 35a, 35b and flow rate detectors 36a, 36 are installed in order.
The outside air intake pipe 42 of the air supply chamber 4 is connected to the exhaust duct 28 located between Moreover, since the reactor building 1 is equipped with a differential pressure transmitter 45 that detects and transmits the differential pressure in the reactor building 1, when the emergency gas treatment system is activated, the inside of the reactor building 1 is This not only prevents abnormal negative pressure, but also prevents the surging phenomenon of the exhaust fans 39a and 39b, and also allows for independent test operation of the emergency gas treatment system.
図は本発明による非常ガス処理装置を示す系統
図である。
1…原子炉建屋、4…給気チヤンバ、5…給気
ダクト、21…主排気筒、22…主排気ダクト、
28…排気ダクト、35a,35b…隔離弁、3
6a,36b…流量検出器、37a,37b…フ
イルタートレイン、38a,38b…流量制御
弁、39a,39b…排風機、42…外気取入れ
管、43…逆止ダンパー、44…流量コントロー
ル弁、45…差圧発信器。
The figure is a system diagram showing an emergency gas treatment device according to the present invention. 1... Reactor building, 4... Air supply chamber, 5... Air supply duct, 21... Main exhaust stack, 22... Main exhaust duct,
28...Exhaust duct, 35a, 35b...Isolation valve, 3
6a, 36b...Flow rate detector, 37a, 37b...Filter train, 38a, 38b...Flow rate control valve, 39a, 39b...Exhaust fan, 42...Outside air intake pipe, 43...Check damper, 44...Flow rate control valve, 45... Differential pressure transmitter.
Claims (1)
並列に設け、この排気ダクトに隔離弁、流量検出
器、フイルタートレイン、流量制御弁及び排風機
を順に設置し、上記隔離弁と流量検出器との間に
位置する上記排気ダクトに給気チヤンバーの外気
取入れ管を接続し、この外気取入れ管に逆止ダン
パー及び流量コントロール弁を設け、この流量コ
ントロール弁に接続され、しかも、上記原子炉建
屋の差圧を検出して発信する差圧発信器を上記原
子炉建屋に設けたことを特徴とする非常ガス処理
装置。1. An exhaust duct is installed in parallel between the reactor building and the main exhaust stack, and an isolation valve, a flow rate detector, a filter train, a flow control valve, and an exhaust fan are installed in this exhaust duct in this order, and the isolation valve and flow rate detection The outside air intake pipe of the supply air chamber is connected to the exhaust duct located between the reactor and the reactor, and the outside air intake pipe is provided with a check damper and a flow rate control valve, and is connected to the flow rate control valve. An emergency gas processing device characterized in that the reactor building is provided with a differential pressure transmitter that detects and transmits a differential pressure in the building.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56056827A JPS57171300A (en) | 1981-04-15 | 1981-04-15 | Emergency gas processing device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56056827A JPS57171300A (en) | 1981-04-15 | 1981-04-15 | Emergency gas processing device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57171300A JPS57171300A (en) | 1982-10-21 |
| JPS6249958B2 true JPS6249958B2 (en) | 1987-10-22 |
Family
ID=13038204
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56056827A Granted JPS57171300A (en) | 1981-04-15 | 1981-04-15 | Emergency gas processing device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57171300A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6080400U (en) * | 1983-11-01 | 1985-06-04 | 石川島播磨重工業株式会社 | Off gas treatment equipment |
| JP5542471B2 (en) * | 2010-02-12 | 2014-07-09 | 日立Geニュークリア・エナジー株式会社 | Waste gas treatment system and waste gas treatment method |
-
1981
- 1981-04-15 JP JP56056827A patent/JPS57171300A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57171300A (en) | 1982-10-21 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109915980B (en) | Ventilation system for nuclear auxiliary workshop of nuclear power plant | |
| JP2011027308A (en) | Ventilation method of central control room and central control room ventilation device | |
| CN105374406B (en) | Ventilation method and system equipment for fast reactor sodium fire accident smoke discharge | |
| JPS6249958B2 (en) | ||
| CN113356915A (en) | Cable tunnel ventilation system and method | |
| JP2963728B2 (en) | Emission radioactivity reduction device | |
| CN116857740A (en) | A kind of air-proof basement ventilation protection equipment | |
| JP2998571B2 (en) | Gas turbine protection device for exhaust reburning combined plant | |
| CN110762801B (en) | Nuclear power plant containment ventilation control method and system | |
| JPS6333193Y2 (en) | ||
| JPH0673421A (en) | Device for controlling change-over of valve for blasting and hot blast system in hot stove | |
| KR102947356B1 (en) | Nuclear fuel manufacturing facility safety system using air conditioning facilities | |
| JPH08304592A (en) | Emergency gas processing equipment | |
| CN218941602U (en) | A Ventilation System for the Test Hall of High Voltage Electrical Equipment | |
| RU2725044C1 (en) | Mobile degassing complex | |
| JPS5823537B2 (en) | Indoor abnormal negative pressure prevention device | |
| JPS5852542A (en) | Monitoring controller of radioactive waste gas leakage | |
| JPH0634065B2 (en) | Ventilation and air conditioning equipment for nuclear power plants | |
| JPH04363695A (en) | Pressure suppression device for nuclear reactor building | |
| CN211505123U (en) | Explosion-proof dust meter | |
| JP3091519B2 (en) | Nuclear power plant turbine building ventilation and air conditioning equipment | |
| JPS6055038B2 (en) | Emergency gas processing method | |
| JPH02275398A (en) | Venting device of reactor container | |
| CN121583600A (en) | Ventilation system and nuclear material production line building for nuclear materials production line | |
| CN119063130A (en) | A negative pressure weighing chamber, air curtain partition assembly and control system thereof |