JPS60202390A - Core cooling device for emergency - Google Patents

Core cooling device for emergency

Info

Publication number
JPS60202390A
JPS60202390A JP59058278A JP5827884A JPS60202390A JP S60202390 A JPS60202390 A JP S60202390A JP 59058278 A JP59058278 A JP 59058278A JP 5827884 A JP5827884 A JP 5827884A JP S60202390 A JPS60202390 A JP S60202390A
Authority
JP
Japan
Prior art keywords
core
emergency
spray
coolant
reactor
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
JP59058278A
Other languages
Japanese (ja)
Inventor
富永 研司
安島 俊夫
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.)
Hitachi Engineering Co Ltd
Hitachi Ltd
Original Assignee
Hitachi Engineering Co Ltd
Hitachi 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 Hitachi Engineering Co Ltd, Hitachi Ltd filed Critical Hitachi Engineering Co Ltd
Priority to JP59058278A priority Critical patent/JPS60202390A/en
Publication of JPS60202390A publication Critical patent/JPS60202390A/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

  • Furnace Details (AREA)
  • Details Of Measuring And Other Instruments (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】 〔発明の利用分野〕 本兄明は沸騰水形原子炉の冷却材喪失事故(LOCA)
時に炉心を冷却する非常炉心冷却装置に関するものでる
る。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to loss of coolant accident (LOCA) in a boiling water nuclear reactor.
Related to the emergency core cooling system that occasionally cools the reactor core.

〔発明の背量」 第1図は沸騰水形原子炉を示したもので、万一のLOC
Aを想定した場合に炉心を十分に冷却するよう非常用炉
心冷却系とじ七高圧注水系1及び炉心スプレィ系2を設
けである。炉心スプレィは炉心3とシュラウドヘッド4
0間に設けられている。
[Backbone of the invention] Figure 1 shows a boiling water reactor, and in the event of an LOC
In order to sufficiently cool the core in case A is assumed, an emergency core cooling system, a high-pressure water injection system 1, and a core spray system 2 are installed. Core spray is for core 3 and shroud head 4
It is set between 0 and 0.

第2図はオーバーへラドスパーンャ方式を示したもので
ある。冷却材はスプレィ配管から、シュラウド側壁に沿
りた主ヘッダ管5に送られさらに、技ヘッダ管6を追っ
て、複数個のスプレィノズル7から燃料集合体8に散水
される。
FIG. 2 shows the Overherd Radspancher method. The coolant is sent from the spray pipe to the main header pipe 5 along the side wall of the shroud, followed by the main header pipe 6, and sprayed onto the fuel assembly 8 from a plurality of spray nozzles 7.

炉心スプレィ系2は、再vti環配管の大破断のように
炉心が露出するLOCA時に炉心を上部から直接スプレ
ィ水によシ冷却する系統である。
The core spray system 2 is a system that cools the core by spraying water directly from above in the event of a LOCA where the core is exposed, such as a major rupture in the re-vti ring pipe.

一方、冷却材の注入配管高さが炉心頂部近傍にあると、
万一の炉心スプレィ配管10の自己破断時には、この注
入配管を介してシュラウド内側の冷却材を放出し、かつ
、自己破断によ#)ECC8系統の一つが既に機能表失
しているので厳しい結果を与えることになぁ。
On the other hand, if the coolant injection pipe height is near the top of the core,
In the event that the core spray pipe 10 self-ruptures, the coolant inside the shroud will be released through this injection pipe, and the self-rupture will cause serious consequences as one of the eight ECC systems has already lost its functionality. I would like to give it to you.

しかし、かかる場合にも十分な炉心冷却ができるよう非
常用炉心冷却系の容量を設計している。
However, the capacity of the emergency core cooling system is designed to ensure sufficient core cooling even in such cases.

〔発明の目的〕[Purpose of the invention]

本発明は、LOCA時炉心全炉心却するスプレィ系にお
いて、スプレィヘッダ管を高くすることにより万一のス
プレィ配管の自己破断に対してよシ安全性を向上させる
とともにスプレィ冷却の必要容量を低減し合理化を図る
こと全目的とする。
The present invention improves safety against self-rupture of the spray piping by increasing the height of the spray header pipe in a spray system that cools the entire reactor core during LOCA, and reduces the required capacity for spray cooling. The entire purpose is to streamline the process.

〔発明のり元要〕[Source of invention]

本発明は、LOC八時へスプレィが注水した場合に周辺
バイパス部に冷却材が落下する傾向が実験的に確認され
ていることから、スパージャを介して注入しなくても炉
心バイパス部が満水になるとオーバーフローで各チャ/
坏ル内に冷却材が注入されることを考慮したものである
The present invention has been experimentally confirmed that when spray water is injected into the 8 o'clock LOC, there is a tendency for coolant to fall into the peripheral bypass area. Then, each cha/
This takes into consideration the fact that a coolant is injected into the ball.

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

次に本発明に係る非常用炉心冷却装置の一実施例を第3
図及び第4図によって説明する。
Next, a third embodiment of the emergency core cooling system according to the present invention will be described.
This will be explained with reference to the drawings and FIG.

I)実施例の構成 本発明の非常用炉心冷却装置は、第3図に示すようにベ
ッセル9内に引込まれたスプレィ配管lOが上部シュラ
ウドヘッド4内で側壁に沿って垂直に立ち上げられ、上
部シュラウド4内で最も高くなる(燃料棒頂部から2f
t以上)位置で直接炉心部に注水される。
I) Configuration of Embodiment In the emergency core cooling system of the present invention, as shown in FIG. It is the highest in the upper shroud 4 (2f from the top of the fuel rods)
Water is injected directly into the reactor core at a position greater than or equal to t.

1i>LOCA時炉心冷却の現象 第4図ぐよ、LOCA時において本発明の炉心スプレィ
系が作動した場合の燃料集合体8内の挙動を示す。
1i>Phenomenon of core cooling during LOCA Figure 4 shows the behavior within the fuel assembly 8 when the core spray system of the present invention is activated during LOCA.

炉心部からの吹き上げ蒸気11によって、スプレィ水1
2が燃料集合体の上部にある程匪溜シ、その後スプレィ
水の動圧によって炉心バイパス13部に落下し始める。
Spray water 1 is generated by blowing up steam 11 from the reactor core.
2 is at the top of the fuel assembly, and then begins to fall into the core bypass section 13 due to the dynamic pressure of the spray water.

それによって、炉心バイパス部が満水になるとオーバー
フローで各チキンネル内に冷却材が注入される。
As a result, when the core bypass section becomes full of water, coolant is injected into each chicken channel as an overflow.

111)効果 本発明の実施によって下記の効果がある。111) Effect Implementation of the present invention has the following effects.

(a) スプレィ配管の出口から直接炉心にスプレィさ
れることにより、従来の配管からヘッダを通ってノズル
から注水される場合より、配管に生ずる差圧が小さくな
る。また、冷却材を送り出すためのポンプの水頭圧も小
さくなる。
(a) By spraying the reactor core directly from the outlet of the spray piping, the differential pressure generated in the piping is smaller than when water is injected from the conventional piping through the header and from the nozzle. Furthermore, the water head pressure of the pump for pumping out the coolant is also reduced.

(b) シュラウドヘッド内に配置されるこれまでのヘ
ッダ、ノズルの変わシに配管1つとなるために炉内構造
が簡略化される。
(b) In place of the conventional header and nozzle placed inside the shroud head, there is only one pipe, which simplifies the furnace internal structure.

(C) 図−5に示すようにスプレィ配管の出口部のエ
レベーションが高くなることによってスプレィの必要量
hiが低減出来る。
(C) As shown in Figure 5, the required amount of spray hi can be reduced by increasing the elevation of the outlet of the spray pipe.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、所定の安全性を確保し、システムのr
+fi ふ化が成し得るので、コスト低減に大きく′舒
与する。又、スプレィ配管の自己破断に対してより安全
性を向上さ、Cることか出来る。
According to the present invention, a predetermined safety is ensured and the r
+fi Since hatching can be achieved, it greatly contributes to cost reduction. Additionally, safety can be further improved against self-rupture of the spray piping.

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

g(51図は現行の沸騰水形原子炉を示す図、第2図は
オーバーへラドスパーンャ方式を示す図、第3図は本発
明の非常用炉心冷却装置を採用した沸騰水形原子炉を示
す図、第4図は燃料集合体内の冷却材の挙動を示す図、
第5図はスプレィ配管のエレベーションに対する必要量
の関係図を示す。
g (Figure 51 shows the current boiling water reactor, Figure 2 shows the over-rad spanner system, and Figure 3 shows the boiling water reactor adopting the emergency core cooling system of the present invention. Figure 4 is a diagram showing the behavior of the coolant in the fuel assembly,
FIG. 5 shows a diagram of the relationship between the required amount and the elevation of the spray piping.

Claims (1)

【特許請求の範囲】 1、軽水型原子炉の原子炉冷却材喪失事故時に冷却材を
シュラウド内側の上部プレナムに直接注入できることを
特徴とする非常用炉心冷却装置。 2、特許請求の範囲第1項において、冷却材の注入口を
1つにし、注入配管の高さ位置を炉心頂部より2ft以
上高くすることを特徴とする非常用炉心冷却系−18 3、特許請求の範囲第2項または第3項において、冷却
月の注入配管をシュラウドヘッド胴部ケ貝通してベッセ
ルから入って来た位置よシ、さらに垂直方向に延長させ
、上部プレナムの上方、炉心頂部よ!112ft以上の
高さから炉心部・\注水することを特徴とする非常用炉
心冷却装置。
[Scope of Claims] 1. An emergency core cooling system characterized by being capable of directly injecting coolant into an upper plenum inside a shroud in the event of a reactor coolant loss accident in a light water reactor. 2. Claim 1: Emergency core cooling system-18, characterized in that the number of coolant injection ports is one, and the height of the injection pipe is set at least 2 ft higher than the top of the core. 3. Patent In claim 2 or 3, the injection pipe for the cooling moon is passed through the shell of the shroud head body to the position where it enters from the vessel, and is further extended vertically to the top of the core above the upper plenum. Yo! An emergency core cooling system that injects water into the reactor core from a height of 112 feet or more.
JP59058278A 1984-03-28 1984-03-28 Core cooling device for emergency Pending JPS60202390A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59058278A JPS60202390A (en) 1984-03-28 1984-03-28 Core cooling device for emergency

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59058278A JPS60202390A (en) 1984-03-28 1984-03-28 Core cooling device for emergency

Publications (1)

Publication Number Publication Date
JPS60202390A true JPS60202390A (en) 1985-10-12

Family

ID=13079717

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59058278A Pending JPS60202390A (en) 1984-03-28 1984-03-28 Core cooling device for emergency

Country Status (1)

Country Link
JP (1) JPS60202390A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH05237473A (en) * 1992-02-26 1993-09-17 Mamii Wear-:Kk Water purifier

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH05237473A (en) * 1992-02-26 1993-09-17 Mamii Wear-:Kk Water purifier

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