JPS5821197A - Emergency core cooling system of atomic power plant - Google Patents

Emergency core cooling system of atomic power plant

Info

Publication number
JPS5821197A
JPS5821197A JP56119749A JP11974981A JPS5821197A JP S5821197 A JPS5821197 A JP S5821197A JP 56119749 A JP56119749 A JP 56119749A JP 11974981 A JP11974981 A JP 11974981A JP S5821197 A JPS5821197 A JP S5821197A
Authority
JP
Japan
Prior art keywords
core cooling
water injection
power plant
piping
cooling water
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
JP56119749A
Other languages
Japanese (ja)
Inventor
桝田 藤夫
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 JP56119749A priority Critical patent/JPS5821197A/en
Publication of JPS5821197A publication Critical patent/JPS5821197A/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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Greenhouses (AREA)
  • Apparatus For Radiation Diagnosis (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】 この発明は原子力発電所の冷却材喪失事故等の異常事態
に対撚する非常用炉心冷却装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an emergency core cooling system for dealing with abnormal situations such as a loss of coolant accident in a nuclear power plant.

一般に、沸騰水型原子力発電所に使用されている非常用
炉心冷却装置は、第1図に示された構成を有し、原子炉
格納容器1内の原子炉圧力容器2に、複数の炉心冷却水
注水配管3,4,5,6゜7がそれぞれ接続されている
。各炉心冷却水注水配管3,4,5,6.7は互いに独
立しており。
In general, an emergency core cooling system used in a boiling water nuclear power plant has the configuration shown in FIG. Water injection pipes 3, 4, 5, and 6°7 are connected to each other. Each core cooling water injection pipe 3, 4, 5, 6.7 is independent from each other.

各注水ポンプ8a 、8b 、8 c 、8d 、8e
からの冷却水が原子炉圧力容器2内に注水されるように
なっている。
Each water injection pump 8a, 8b, 8c, 8d, 8e
Cooling water from the reactor pressure vessel 2 is injected into the reactor pressure vessel 2.

各炉心冷却水注水配管は、原子炉格′納谷器lの外側に
常閉の隔離弁9a、9b、9c、9d、9eおよび逆止
弁]、Oa 、 lOb 、 lOa 、 10d’、
 10eをそtぞれ直列に配設しており、原子炉圧力容
器2内へ注水する機態に応じて、高圧炉心スプレィ系配
管3.低圧炉心スジレイ系配管4.低圧注水系配管5,
6.7に分けられる。
Each core cooling water injection pipe is provided with normally closed isolation valves 9a, 9b, 9c, 9d, 9e and check valves on the outside of the reactor enclosure l, Oa, lOb, lOa, 10d',
10e are arranged in series, and depending on the mechanism for injecting water into the reactor pressure vessel 2, high pressure core spray system piping 3. Low pressure core line system piping 4. Low pressure water injection system piping 5,
It is divided into 6.7.

しかして、何らかの原因で原子炉圧力容器2内の水位が
低下する冷却材喪失事故が発生した場合。
However, if a coolant loss accident occurs in which the water level in the reactor pressure vessel 2 drops for some reason.

非常用炉心冷却装置の注水ポンプ8a〜8eが一斉に起
動されて、隔離弁9a〜9eが開き、原子炉圧力容器2
内に冷却水が注水され、原子力発電所内での事故を未然
に防止している。
The water injection pumps 8a to 8e of the emergency core cooling system are started all at once, the isolation valves 9a to 9e are opened, and the reactor pressure vessel 2
Cooling water is injected into the reactor to prevent accidents within the nuclear power plant.

このとき、常閉隔離弁9a〜9@が同時に開き。At this time, the normally closed isolation valves 9a to 9@ open simultaneously.

各注水tieンプ8a〜8eが同時に起動するように。Each water injection tie pump 8a to 8e is activated at the same time.

各ポンプおよび升類は充分な品質管理が行なわれており
、信頼度は高い。
Each pump and box has undergone sufficient quality control and is highly reliable.

しかしながら5万一注水ポンプ8aおよび隔離弁9bが
故障して動作しない場合が生じたとすると、他の注水ポ
ンプ8b〜8・、隔離弁9a、9a〜9eが正常に動作
しても、2系統の炉心冷却水注水配管3.4は冷却水注
水機能を失ない、原子炉圧力容器2内を充分に冷却する
ことができない恐れがめつto この発明は上述した点を考慮し、各炉心冷却水注水配管
を連絡配管で接続することにより、各炉心冷却水注水配
管の機能を相互に補償し、冷却材喪失事故等の異常事態
にも有効に対撚し得るようにした原子力発電所の非常用
炉心冷却装置を提供することを目的とする。
However, in the unlikely event that the water injection pump 8a and isolation valve 9b fail and do not operate, even if the other water injection pumps 8b to 8 and isolation valves 9a and 9a to 9e operate normally, the two systems There is a risk that the core cooling water injection piping 3.4 will not lose its cooling water injection function and the inside of the reactor pressure vessel 2 will not be able to be sufficiently cooled. By connecting the core cooling water injection pipes with connecting pipes, the functions of each core cooling water injection pipe are mutually compensated, and the emergency core cooling system of a nuclear power plant is designed to effectively cope with abnormal situations such as loss of coolant accidents. The purpose is to provide equipment.

以下5この発明に係る原子力発電所の非常用炉心冷却装
置の実MNについて説明する。
The actual MN of the emergency core cooling system for a nuclear power plant according to the present invention will be explained below.

第2図において、符号20は沸騰水型原子力発電所に組
み込まれる原子炉格納茶器を示し、この原子炉格納茶器
加内に原子炉圧力容器21が収納されている。原子炉圧
力容器21内に炉心部22が構成さnる。
In FIG. 2, reference numeral 20 indicates a reactor containment tea utensil installed in a boiling water nuclear power plant, and a reactor pressure vessel 21 is housed inside this reactor containment tea utensil. A reactor core portion 22 is configured within the reactor pressure vessel 21 .

原子炉圧力容器21には複数の独豆した炉心冷却水注水
配管23 、24 、25 、26 、27がそrぞれ
接続さnる。各炉心冷却水注水配管23〜27ニ原子炉
格納容器かの隔壁を貫いて外部に突出し、途中に常閉の
隔離弁28a〜詔・および逆止弁29a〜29aを介し
て注水ポンプ30 a = 30 e にそれぞれ接続
される。
A plurality of independent core cooling water injection pipes 23 , 24 , 25 , 26 , and 27 are connected to the reactor pressure vessel 21 , respectively. Each of the core cooling water injection pipes 23 to 27 protrudes to the outside through the partition wall of the reactor containment vessel, and is connected to a water injection pump 30a through normally closed isolation valves 28a to 29a and check valves 29a to 29a. 30 e respectively.

各炉心冷却水注水配管る〜nは用途9機能に応じて高圧
炉心スプレィ系配管乙および低圧炉心スジレイ系配管為
、低圧炉心注水系配管δ〜nに分けられる。
Each core cooling water injection piping ~n is divided into high pressure core spray system piping B, low pressure core spray system piping, and low pressure core water injection system piping δ~n according to the function of use.

各炉心注水系配管zつ〜27は常閉の隔離弁28a〜夙
・と逆止弁29a〜29mとの間で連絡配管あて接続さ
れる。連絡配管35は閉じたループを構成している。連
絡配管あには各炉心冷却用注水配管お〜nの各結合部(
接続部)との間に、少なくとも11固の常閉隔離弁36
a〜36・が設けられている。
Each of the core water injection system pipes 27 to 27 is connected to a communication pipe between the normally closed isolation valves 28a to 28 and the check valves 29a to 29m. The connecting pipe 35 constitutes a closed loop. Connecting piping A is connected to each joint of each core cooling water injection pipe O~n (
at least 11 normally-closed isolation valves 36 between the
A to 36. are provided.

なお、第2図において、符号37.38は冷却水循環系
統を示し、39a〜39oは非常時に注水ポンプ30a
〜30eを駆動させる非常用ディーゼル発電機である。
In addition, in FIG. 2, numerals 37 and 38 indicate the cooling water circulation system, and 39a to 39o indicate the water injection pump 30a in case of an emergency.
This is an emergency diesel generator that drives the ~30e.

各注水ポンプ30a〜30eはいずれもほぼ同程度のポ
ンプ容量を有し、互換使用できる。
Each of the water injection pumps 30a to 30e has approximately the same pump capacity and can be used interchangeably.

次に、この発明の作用について説明する。Next, the operation of this invention will be explained.

原子力発電所の冷却材喪失事故が起ると、原子炉圧力容
器21内の冷却水が失なわれ、水位が異常に低下する。
When a loss of coolant accident occurs in a nuclear power plant, the cooling water in the reactor pressure vessel 21 is lost and the water level drops abnormally.

この水位低下を図示しない検知器で検出し、各注水ポン
プ30&〜30eを起動させるとともに各隔離弁28a
〜28aを開く。これにより、各注水ポンプ30a〜3
0sからの冷却水が炉心冷却用注水配管n〜nを通って
原子炉圧力容器21内の炉心部22に供給され、この炉
心部ρを冷却する。
This drop in water level is detected by a detector (not shown), and each water injection pump 30 & ~ 30e is activated, and each isolation valve 28a is activated.
~Open 28a. As a result, each water injection pump 30a to 3
Cooling water from 0s is supplied to the reactor core 22 in the reactor pressure vessel 21 through core cooling water injection pipes n to n to cool the reactor core ρ.

このとき、仮に注水ポンプ30 aが起動せず、隔離弁
28bが開かなかったとすると、他の各注水ポンプ30
 b −3Q eおよび隔離弁28 a 、 28 e
 〜28 eが正常に動作しても、原子炉圧力容器21
内に注水される冷却水は注水ポンプ30c〜30eから
吐出されたものだけであり、この注水状態ぼ中央運転室
内の表示盤に表示される。
At this time, if the water injection pump 30a does not start and the isolation valve 28b does not open, each of the other water injection pumps 30a
b-3Qe and isolation valves 28a, 28e
~28 Even if e operates normally, the reactor pressure vessel 21
The cooling water injected into the interior is only that discharged from the water injection pumps 30c to 30e, and the state of this water injection is displayed on the display panel in the central operation room.

したがって運転員が上記表示盤による表示を確認して5
隔離升36bを開くことにより、注水ポンプ30bから
吐出された冷却水を逆止弁29b、隔離弁36bおよび
28aを介して原子炉圧力容器21内に送り込むことが
できる。したがって、連絡配管35と各隔離弁36a〜
36eをそれぞれ設けることにより、従来無駄になって
いた注水ポンプからの冷却水を有効に活用することがで
きる。
Therefore, the operator should check the display on the above display panel and
By opening isolation box 36b, cooling water discharged from water injection pump 30b can be sent into reactor pressure vessel 21 via check valve 29b, isolation valves 36b and 28a. Therefore, the connecting pipe 35 and each isolation valve 36a~
36e, the cooling water from the water injection pump, which was wasted in the past, can be effectively utilized.

また、注水ポンプ30cと隔離弁28eが故障しt場合
を想定すると、この場合には、隔離9P36d。
Further, assuming that the water injection pump 30c and isolation valve 28e fail, in this case, isolation 9P36d.

36 eをそれぞれ開ぐことにより、注水ポンプ30d
By opening 36e, the water injection pump 30d
.

30eの冷却水を隔離弁28 c 、 28 d  を
介して原子炉圧力容器21内に注水することができる。
The cooling water 30e can be injected into the reactor pressure vessel 21 through the isolation valves 28c, 28d.

したがって、故障機器が隣り合った配管系統以外に存在
しても、冷却水を有効的に注水させることができる。
Therefore, even if a failed device exists in a piping system other than the adjacent piping system, cooling water can be effectively injected.

なお、この発明の詳細な説明においてに、連絡配管35
の各隔離弁36a〜36eの操作を運転員が行なう場合
について説明したが、自動的に行ない得ることは勿論で
ある。
In addition, in the detailed description of this invention, the connecting pipe 35
Although the case where the operator operates each of the isolation valves 36a to 36e has been described, it is of course possible to operate the isolation valves 36a to 36e automatically.

また、−更施例では沸騰水型原子力発電所にこの発明を
適用した例について説明したが、必ずしも沸騰水型に限
定されず、他の型の原子力発電所にこの発明を適用して
もよい。
Further, in the following example, an example in which the present invention is applied to a boiling water type nuclear power plant has been described, but the present invention is not necessarily limited to a boiling water type nuclear power plant, and may be applied to other types of nuclear power plants. .

また、連絡配管を二本以上並列に接続するようにしても
よい。
Furthermore, two or more connecting pipes may be connected in parallel.

以上に述べたように、この発明に係る原子力発電所の非
常用炉心冷却H1tにおいては、複数のそれぞれ独立し
た炉心冷却水注水配管を連絡用配管でそれぞn接続した
から、各炉心冷却水注水配管の各機器が複数箇所で故障
しても、各炉心冷却水注水配管の各機能を相互に補償し
、悪影響を最小限に保つことができるので、冷却材喪失
事故等にも有効に対撚することができ、原子力発電所の
安全性を大きく同士させることができる等の効果を奏す
る。
As described above, in the emergency core cooling H1t of a nuclear power plant according to the present invention, since a plurality of independent core cooling water injection pipes are connected by connecting pipes, each core cooling water injection Even if piping equipment breaks down at multiple locations, each function of each core cooling water injection piping can be mutually compensated and adverse effects can be kept to a minimum, making it an effective countermeasure against coolant loss accidents. This has the effect of significantly improving the safety of nuclear power plants.

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

第1図は沸騰水型原子力発電所における従来の非常用炉
心冷却装置を示す図5第2図はこの発明に係る原子力発
電所の非常用炉心冷却装着の一夾施例を示す図である。 20・・・原子炉格納容器、2j・・・原子炉圧力容器
。 22・・・炉心部、23〜27・・・炉心冷却用注水配
管、28a〜28e−隔離弁、29a 〜29e−逆I
E升、 30a 〜30e・・・注水ポンプ、35・・
・連絡配管、36a〜あθ・・・隔離弁・ 出願人代理人   猪 股    清
FIG. 1 shows a conventional emergency core cooling system for a boiling water nuclear power plant. FIG. 2 shows an embodiment of an emergency core cooling system for a nuclear power plant according to the present invention. 20...Reactor containment vessel, 2j...Reactor pressure vessel. 22... Core part, 23-27... Water injection piping for core cooling, 28a-28e-isolation valve, 29a-29e-inverted I
E-sho, 30a ~ 30e... Water pump, 35...
・Connection piping, 36a~aθ...isolation valve・Applicant's agent Kiyoshi Inomata

Claims (1)

【特許請求の範囲】 1、逆止弁および常閉隔離弁をそれぞれ有する複数の独
立した炉心冷却用注水配管を原子炉圧力容器に接続し、
冷却材喪失事故等の非常時に上記炉心冷却用注水配管を
通して冷却水を原子炉圧力容器内に注水するようにした
原子力発電所の非常用炉心冷却装置くおいて、各炉心冷
却用注水配管は連絡配管でそれぞれ相互に接続されたこ
とを特徴とする。原子力発電所の非常用炉心冷却装置。 2、連絡配管は各炉心冷却用配管の逆止弁と常閉隔離弁
との間に接続されて閉じたループを形成した特許請求の
範囲第1項に記載の原子力発電所の非常用炉心冷却装置
。 3、連絡配管は各炉心冷却用配管の接続部の間に少なく
とも1飼の常閉隔離弁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炉心冷却装置。
[Claims] 1. Connecting a plurality of independent core cooling water injection pipes each having a check valve and a normally closed isolation valve to a reactor pressure vessel,
In the emergency core cooling system of a nuclear power plant, which injects cooling water into the reactor pressure vessel through the core cooling water injection piping in the event of an emergency such as a loss of coolant accident, each core cooling water injection piping is connected. They are characterized by being connected to each other by piping. Emergency core cooling system at a nuclear power plant. 2. Emergency core cooling of a nuclear power plant according to claim 1, wherein the connecting pipe is connected between the check valve of each core cooling pipe and the normally closed isolation valve to form a closed loop. Device. 3. The emergency core cooling system for a nuclear power plant according to claim 1, wherein the communication piping has at least one normally closed isolation valve between the joints of each core cooling piping.
JP56119749A 1981-07-30 1981-07-30 Emergency core cooling system of atomic power plant Pending JPS5821197A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56119749A JPS5821197A (en) 1981-07-30 1981-07-30 Emergency core cooling system of atomic power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56119749A JPS5821197A (en) 1981-07-30 1981-07-30 Emergency core cooling system of atomic power plant

Publications (1)

Publication Number Publication Date
JPS5821197A true JPS5821197A (en) 1983-02-07

Family

ID=14769191

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56119749A Pending JPS5821197A (en) 1981-07-30 1981-07-30 Emergency core cooling system of atomic power plant

Country Status (1)

Country Link
JP (1) JPS5821197A (en)

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