JPS58113892A - Main steam isolation valve leakage suppression device - Google Patents

Main steam isolation valve leakage suppression device

Info

Publication number
JPS58113892A
JPS58113892A JP56211069A JP21106981A JPS58113892A JP S58113892 A JPS58113892 A JP S58113892A JP 56211069 A JP56211069 A JP 56211069A JP 21106981 A JP21106981 A JP 21106981A JP S58113892 A JPS58113892 A JP S58113892A
Authority
JP
Japan
Prior art keywords
main steam
isolation valve
steam isolation
steam pipe
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.)
Pending
Application number
JP56211069A
Other languages
Japanese (ja)
Inventor
黒田 義博
健司 新井
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 Corp
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Nippon Genshiryoku Jigyo KK
Tokyo Shibaura Electric Co Ltd
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 Nippon Genshiryoku Jigyo KK, Tokyo Shibaura Electric Co Ltd, Nippon Atomic Industry Group Co Ltd filed Critical Nippon Genshiryoku Jigyo KK
Priority to JP56211069A priority Critical patent/JPS58113892A/en
Publication of JPS58113892A publication Critical patent/JPS58113892A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Control Of Turbines (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 本発明は沸騰水形原子炉の主蒸気隔離弁漏洩抑制装置に
関する。
TECHNICAL FIELD OF THE INVENTION The present invention relates to a main steam isolation valve leakage suppression system for a boiling water nuclear reactor.

発明の技術的背景とその問題点 沸騰水形原子力発電所においては、沸騰水形原子炉にて
冷却材である水を蒸気にし、この蒸気を主蒸気管を介し
てタービン(=送り発電機を運転する。主蒸気管(−は
複数個の主蒸気隔離弁を設けであるが、最下流側の主蒸
気隔離弁より下流のタービン側主蒸気管は構造上破断す
ることがあり得る。
Technical background of the invention and its problems In a boiling water nuclear power plant, water, which is a coolant, is turned into steam in a boiling water reactor, and this steam is sent to a turbine (= feed generator) through a main steam pipe. The main steam pipe (- indicates that a plurality of main steam isolation valves are installed, but the turbine side main steam pipe downstream of the most downstream main steam isolation valve may be structurally broken.

この原子炉の運転中に何らかの原因(二より主蒸気管が
破断すると、破断口から原子炉内の冷却材の流出が起こ
り、核分裂生成物が直接発電所敷地内に放出される可能
性があるので、破断じよシ発せられる主蒸気管流最大、
主蒸気圧力像等の信号で主蒸気管の原子炉格納容器貫通
部の両側(−設置されている主蒸気隔離弁を自動閉鎖さ
せて冷却材の放出を抑えるようにしている。しかし、主
蒸気隔離弁閉鎖後原子炉圧力は定格運転圧力近傍(=保
持され、高圧であるため(二、主蒸気隔離弁を通って原
子炉内蒸気が僅かながら漏洩して行く可能性がある。従
来の主蒸気隔離弁漏洩抑制装置は主蒸気管(−1原子炉
側からタービン側へと第1、第2、第3と3個の主蒸気
隔離弁を直列に介在させており、第3主蒸気隔離弁より
タービン側の主蒸気管に破断の確率があるので、第1主
蒸気隔離弁と第2主蒸気隔離弁との間の前側主蒸気管、
又は第2主蒸気隔離弁と第3主蒸気隔離弁との間の後側
主蒸気管(二漏洩して来た蒸気をサプレッションプール
(二放出することにより、第3主蒸気隔離弁を通して破
断口から漏洩する蒸気量をさらに減少させているが、そ
れでも未だ不十分であると考えられている。
If the main steam pipe ruptures for some reason during the operation of this nuclear reactor, the coolant inside the reactor may flow out from the rupture port, and fission products may be released directly into the power plant premises. Therefore, the main steam pipe flow generated by the rupture is maximum,
Signals such as main steam pressure images are used to automatically close the main steam isolation valves installed on both sides of the main steam pipe's penetration of the reactor containment vessel to suppress the release of coolant. After the isolation valve is closed, the reactor pressure is maintained close to the rated operating pressure (= maintained), and because the pressure is high (2. There is a possibility that a small amount of reactor steam may leak through the main steam isolation valve. The steam isolation valve leakage suppression device has three main steam isolation valves interposed in series from the main steam pipe (-1 reactor side to the turbine side), and the third main steam isolation valve Since there is a probability of rupture in the main steam pipe on the turbine side of the valve, the front main steam pipe between the first main steam isolation valve and the second main steam isolation valve,
Or, the rear main steam pipe between the second main steam isolation valve and the third main steam isolation valve (by releasing the leaked steam into the suppression pool (second), it is passed through the third main steam isolation valve to the rupture port). Although efforts have been made to further reduce the amount of steam leaking from the system, it is still considered insufficient.

発明の目的 本発明の目的は、主蒸気管破断事故時において、主蒸気
隔離弁閉鎖後、主蒸気隔離弁を通して破断口から漏洩す
る蒸気量を極めて低く抑える主蒸気隔離弁漏洩抑制装置
を提供する゛こと(二ある。
OBJECTS OF THE INVENTION An object of the present invention is to provide a main steam isolation valve leakage suppression device that suppresses the amount of steam leaking from a rupture port through the main steam isolation valve to an extremely low level after the main steam isolation valve is closed in the event of a main steam pipe rupture accident. There are two things.

発明の概要 本発明においては、沸騰水形原子炉とタービンをつなぐ
主蒸気管(=複数個の主蒸気隔離弁を直列(−介在させ
、タービン側主蒸気管破断時に、前記   1主蒸気隔
離弁間の主蒸気管に高圧空気供給源から高圧空気を供給
する空気配管を設け、タービン側主蒸気管破断時に前記
主蒸気隔離弁間を高圧空気で満たし、この主蒸気隔離弁
からの蒸気の漏洩を極力抑制する。
Summary of the Invention In the present invention, a main steam pipe connecting a boiling water nuclear reactor and a turbine (= a plurality of main steam isolation valves are connected in series), and when the main steam pipe on the turbine side is ruptured, the first main steam isolation valve An air pipe that supplies high-pressure air from a high-pressure air supply source is installed in the main steam pipe between the main steam pipes, and when the main steam pipe on the turbine side breaks, the space between the main steam isolation valves is filled with high-pressure air, and steam leaks from the main steam isolation valve. suppress as much as possible.

発明の実施例 以下、本発明の一実施例(二ついて、図面を参照して説
明する。
Embodiment of the Invention Hereinafter, one embodiment (two embodiments) of the present invention will be described with reference to the drawings.

図示しない原子炉から原子炉側主蒸気管(1,)を引き
出し、第1主蒸気隔離弁(2)(二接続し、この第1主
蒸気隔離弁(2)から前側主蒸気管(1,)を引き出し
て原子炉格納容器壁(3)を貫通し、第2主蒸気隔離弁
(4)に接続し、この第2主蒸気隔離弁(4)から後側
主蒸気管(13)を引き出して第3主蒸気隔離弁(5)
に接続し、この第3主蒸気隔離弁(5)からタービン側
主蒸気管(14)を引き出して図示しないタービン(二
接続する。次(二図示しないフィルターを介して清浄な
空気を取り入れる高圧空気圧縮機(6)と高圧空気貯槽
(力とを第1空気配管(81)l二より接続する。
A reactor side main steam pipe (1, ), penetrate the reactor containment vessel wall (3), connect to the second main steam isolation valve (4), and pull out the rear main steam pipe (13) from this second main steam isolation valve (4). 3rd main steam isolation valve (5)
The turbine side main steam pipe (14) is pulled out from this third main steam isolation valve (5) and connected to the turbine (not shown). The compressor (6) and the high pressure air storage tank (power) are connected through the first air pipe (81).

高圧空気貯槽(力から第2空気配管(80を引出してこ
れに高圧空気供給弁(9)を設け、それに続く第3空気
配管(80の途中で分岐させた第4空気配管(84)に
安全弁0〔を設ける。第3空気配管(80はさら(=第
5、第6の空気配管(85)、 (8,)に分岐し、第
5空気配管(8,)は原子炉格納容器壁(3)の外側で
第1主蒸気管接続弁αDを介して前側主蒸気管(10に
接続する。第6空気配管(8ρは第2主蒸気管接続弁a
2を介して後側主蒸気管(1◇に接続する。
Pull out the second air pipe (80) from the high-pressure air storage tank and install a high-pressure air supply valve (9) in it, and install a safety valve in the third air pipe (fourth air pipe (84) branched in the middle of 80). 0 [.The third air pipe (80) further branches into the fifth and sixth air pipes (85), (8,), and the fifth air pipe (8,) is connected to the reactor containment vessel wall ( 3) is connected to the front main steam pipe (10) via the first main steam pipe connection valve αD.The sixth air pipe (8ρ is connected to the second main steam pipe connection valve a)
Connect to the rear main steam pipe (1◇) via 2.

次(二作用について説明する。Next (explaining the two effects.

図中、黒塗りした弁は通常運転時閉で、白抜きした弁は
通常運転時開であることを示す。原子炉格納容器壁(3
)外で主蒸気管例えばタービン側主蒸気管(14)が破
断すると、破断口が大気中に開放される為に、破断口か
ら蒸気が急激に放出される。
In the figure, the black valves are closed during normal operation, and the white valves are open during normal operation. Reactor containment vessel wall (3
) When the main steam pipe (14) on the turbine side, for example, breaks outside the main steam pipe (14), the break port is opened to the atmosphere, and steam is rapidly released from the break port.

主蒸気管蒸気流量は急速に増大し、主蒸気管蒸気流量大
の信号が発せられる。この信号により第1、第2、第3
の主蒸気隔離弁(2) 、 (4) 、 (5)は閉鎖
され、破断口からの冷却材の放出を停止しようとする。
The main steam pipe steam flow rate increases rapidly, and a signal indicating a large main steam pipe steam flow rate is generated. This signal causes the first, second, and third
The main steam isolation valves (2), (4) and (5) are closed and attempt to stop the release of coolant from the rupture.

しかし、破断を検知して原子炉がスクラムされても、原
子炉はなお、高圧状態に保たれているので、各主蒸気隔
離弁(2) 、 (4) 、 (5)を通って原子炉内
蒸気が漏出して行き、僅かずつ破断口から放出されるこ
とになる。しかして、高圧空気貯槽(7)には常時高圧
空気が貯蔵されている。主蒸気管蒸気流量大等による主
蒸気管破断発生の信号により、高圧空気圧縮機(6)が
作動し、前記高圧空気貯槽(7)にさら(=高圧空気を
送風する。また同時(=高圧空気供給弁(3)を開にす
る。そして各主蒸気隔離弁(2) 、 (4) 、 (
5)が閉鎖完了したときに両生蒸気管接続弁α1)、α
りを開にし、清浄な高圧空気を前側主蒸気管(10と後
側主蒸気管(13)に注入し、この両生蒸気管(IJ、
(13)内を高圧に保つ。従って原子炉がかなり高圧状
態に保たれている時には、各主蒸気隔離弁(2+ 、 
(4) 、 (5)(二加わる差圧を抑えること(二よ
り、蒸気漏出を低減させることが出来、また原子炉圧力
がある程度減圧され、高圧空気の圧力より低くなると、
高圧空気が第1主蒸気隔離弁(2)を通って原子炉側に
漏洩して行くので、原子炉からの蒸気の漏出は防止され
る。
However, even if a rupture is detected and the reactor is scrammed, the reactor is still maintained at high pressure, so the main steam isolation valves (2), (4), (5) Internal steam leaks out and is released little by little from the fracture opening. Therefore, high pressure air is always stored in the high pressure air storage tank (7). The high-pressure air compressor (6) is activated in response to a signal indicating that the main steam pipe has broken due to a large steam flow rate, etc., and further blows high-pressure air into the high-pressure air storage tank (7). Open the air supply valve (3) and each main steam isolation valve (2), (4), (
5) has completed closing, the two-way steam pipe connection valve α1), α
open, clean high-pressure air is injected into the front main steam pipe (10) and the rear main steam pipe (13), and the double steam pipe (IJ,
(13) Maintain high pressure inside. Therefore, when the reactor is kept at fairly high pressure, each main steam isolation valve (2+,
(4), (5) (2) Suppressing the differential pressure (from 2), steam leakage can be reduced, and when the reactor pressure is reduced to a certain extent and becomes lower than the pressure of high-pressure air,
Since high pressure air leaks to the reactor side through the first main steam isolation valve (2), leakage of steam from the reactor is prevented.

尚、上記において、各主蒸気隔離弁(2) 、 (4)
 、 (5)のいずれかが不動作の場合(二も対処出来
るように、上流側にある第1の主蒸気管接続弁(Ill
は最上流側(二ある第1主蒸気隔離弁(2)の閉完了後
、若干の時間遅れをもって開き、また下流側にある第2
の主蒸気管接続弁azは最下流側にある第3主蒸気隔離
弁(5)の閉完了後、若干の時間遅れをもって開とする
。安全弁Hは過圧防止に役立つ。
In addition, in the above, each main steam isolation valve (2), (4)
, (5) is inoperable (in order to deal with both cases, the first main steam pipe connecting valve (Ill.
After the first main steam isolation valve (2) on the most upstream side (two main steam isolation valves) is closed, it opens with a slight delay, and the second main steam isolation valve on the downstream side
The main steam pipe connection valve az will be opened with a slight delay after the third main steam isolation valve (5) located on the most downstream side has been closed. Safety valve H helps prevent overpressure.

尚、本発明は上記し、かつ図面に示した実施例のみに限
定されるものではなく、その要旨を変更しない範囲で、
種々変更して実施できることは勿論である。
It should be noted that the present invention is not limited to the embodiments described above and shown in the drawings, but may include the following without changing the gist thereof:
Of course, it can be implemented with various modifications.

発明の効果 以上述べたように、本発明によれば、原子炉格納容器外
でのタービン側主蒸気管破断事故(=おいて、複数の主
蒸気隔離弁間の主蒸気管に高圧空気を注入することによ
り高圧に保つようにしたので、主蒸気隔離弁からの蒸気
の漏洩抑制を良好にした主蒸気隔離弁漏洩抑制装置が得
られる。
Effects of the Invention As described above, according to the present invention, high-pressure air is injected into the main steam pipe between a plurality of main steam isolation valves in a turbine-side main steam pipe rupture accident outside the reactor containment vessel. By doing so, the pressure is maintained at a high pressure, so that a main steam isolation valve leakage suppressing device that effectively suppresses leakage of steam from the main steam isolation valve can be obtained.

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

図面は本発明の主蒸気隔離弁漏洩抑制装置の一実施例を
示す管系図である。 ■0.・・原子炉側主蒸気管 1.・・・前側主蒸気管
13・・・後側主蒸気管    14・・・タービン側
主蒸気管2.4.5・・・第1、第2、第3の主蒸気隔
離弁3・・・原子炉格納容器壁   6・・・高圧空気
圧縮機7・・・高圧空気供給源である高圧空気貯槽8、
〜86・・・空気配管   9・・・高圧空気供給弁1
0・・・安全弁 11.12・・・第1、第2の主蒸気管接続弁代理人 
弁理士  井 上 −男
The drawing is a pipe system diagram showing an embodiment of the main steam isolation valve leakage suppressing device of the present invention. ■0. ...Reactor side main steam pipe 1. ...Front side main steam pipe 13...Rear side main steam pipe 14...Turbine side main steam pipe 2.4.5...First, second, third main steam isolation valve 3... Reactor containment vessel wall 6... High pressure air compressor 7... High pressure air storage tank 8 which is a high pressure air supply source,
~86...Air piping 9...High pressure air supply valve 1
0...Safety valve 11.12...1st and 2nd main steam pipe connection valve agent
Patent Attorney Inoue - Male

Claims (2)

【特許請求の範囲】[Claims] (1)沸騰水形原子炉とタービンをつなぐ主蒸気管に複
数個の主蒸気隔離弁を直列に介在させ、タービン側主蒸
気管破断時に、前記主蒸気隔離弁間の主蒸気管;二高圧
空気供給源から高圧空気を供給する空気配管を設けたこ
とを特徴とする主蒸気隔離弁漏洩抑制装置。
(1) A plurality of main steam isolation valves are interposed in series in the main steam pipe connecting the boiling water reactor and the turbine, and when the main steam pipe on the turbine side breaks, the main steam pipe between the main steam isolation valves; two high pressure A main steam isolation valve leakage suppression device characterized by being provided with air piping that supplies high-pressure air from an air supply source.
(2)主蒸気隔離弁は3個直列とし、各主蒸気隔離弁間
の主蒸気管に高圧空気供給源からの空気配管を分岐して
それぞれ主蒸気管接続弁を介して接続し、上流側の主蒸
気管接続弁は最上流側の主蒸気隔離弁の閉完了後若干の
時間遅れをもって開き下流側の主蒸気管接続弁は最下流
側の主蒸気隔離弁の閉完了後若干の時間遅れをもって開
かせたことを特徴とする特許請求の範囲第1項記載の主
蒸気隔離弁漏洩抑制装置。
(2) Three main steam isolation valves are connected in series, and air piping from a high-pressure air supply source is branched to the main steam pipe between each main steam isolation valve and connected via a main steam pipe connection valve, and the upstream side The main steam pipe connection valve opens with a slight delay after the most upstream main steam isolation valve closes, and the downstream main steam pipe connection valve opens with a slight delay after the most downstream main steam isolation valve closes. The main steam isolation valve leakage suppressing device according to claim 1, characterized in that the main steam isolation valve leakage suppressing device is opened by holding the main steam isolation valve open.
JP56211069A 1981-12-28 1981-12-28 Main steam isolation valve leakage suppression device Pending JPS58113892A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56211069A JPS58113892A (en) 1981-12-28 1981-12-28 Main steam isolation valve leakage suppression device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56211069A JPS58113892A (en) 1981-12-28 1981-12-28 Main steam isolation valve leakage suppression device

Publications (1)

Publication Number Publication Date
JPS58113892A true JPS58113892A (en) 1983-07-06

Family

ID=16599885

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56211069A Pending JPS58113892A (en) 1981-12-28 1981-12-28 Main steam isolation valve leakage suppression device

Country Status (1)

Country Link
JP (1) JPS58113892A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109578089A (en) * 2018-12-11 2019-04-05 大唐鸡西热电有限责任公司 300MW critical steam turbine reheating main steam valve valve stem leakoff troubleshooting methodology

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109578089A (en) * 2018-12-11 2019-04-05 大唐鸡西热电有限责任公司 300MW critical steam turbine reheating main steam valve valve stem leakoff troubleshooting methodology

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