JPS58180992A - Reactor - Google Patents

Reactor

Info

Publication number
JPS58180992A
JPS58180992A JP57063893A JP6389382A JPS58180992A JP S58180992 A JPS58180992 A JP S58180992A JP 57063893 A JP57063893 A JP 57063893A JP 6389382 A JP6389382 A JP 6389382A JP S58180992 A JPS58180992 A JP S58180992A
Authority
JP
Japan
Prior art keywords
reactor
cooling water
emergency
pressure vessel
shroud
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
JP57063893A
Other languages
Japanese (ja)
Inventor
渉 佐川
佐藤 佑信
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 Ltd
Original Assignee
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 Ltd filed Critical Hitachi Ltd
Priority to JP57063893A priority Critical patent/JPS58180992A/en
Publication of JPS58180992A publication Critical patent/JPS58180992A/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

  • Treatment Of Water By Oxidation Or Reduction (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】 本発明#i原子炉の非常用冷却装置に係炒、特にシュラ
ウド内の燃料集合体の上方から冷却水を散布するスプレ
ィノズルを有する原子炉に好適な非常用炉心冷却配管に
関する。
Detailed Description of the Invention Emergency core cooling suitable for the emergency cooling system of the present invention #i nuclear reactor, especially for a reactor having a spray nozzle that sprays cooling water from above the fuel assembly in the shroud. Regarding piping.

%1155−164274 に示す如く、原子炉−次冷
却水循壊ポンプを原子炉圧力容器に内蔵した原子炉にお
いて、非常用炉心冷却水をシュラウド内の燃料集合体の
上方から散水冷却する方式と原子炉圧力容器と7ユラウ
ドの間の環状部分に注入しシュラウドサポートレグ金運
し、下方から冷却する方式の2系統の非常用炉心冷却方
式が採用されている。しかし、冷却水tJl11子炉圧
力容器とシュラウドの間の環状部分に注入すると、高温
の容器壁に低温水が直II!当たり、容器壁に急激な熱
衝撃を生じ、容器の健全性が損われる恐れがめる。
%1155-164274, in a nuclear reactor with a sub-reactor cooling water circulation pump built into the reactor pressure vessel, there is a system in which emergency core cooling water is spray-cooled from above the fuel assembly in the shroud. A two-system emergency core cooling system has been adopted: injected into the annular area between the reactor pressure vessel and the 7th floor, and cooled from below through the shroud support leg. However, when cooling water is injected into the annular portion between the reactor pressure vessel and the shroud, low-temperature water flows directly onto the high-temperature vessel wall. This may cause a sudden thermal shock to the container wall, potentially damaging the integrity of the container.

本発明の目的は、上記の従来技術のもつ欠点をなくシ、
原子炉圧力容器の健全性を損うことなく非常時の炉心部
冷却食性うことのできる非常用炉心、注水配管を提供す
るにるる。
The object of the present invention is to eliminate the drawbacks of the above-mentioned prior art;
To provide an emergency core and water injection piping that can cool the reactor core in an emergency without impairing the integrity of the reactor pressure vessel.

本発明の特徴は、原子炉圧力容器ノズルより、シュラウ
ドヘッド上atで炉内配管により接続し、非常用炉心冷
却水tシュラウドヘッド上部に注入することにある。
The feature of the present invention is that the emergency core cooling water is injected from the reactor pressure vessel nozzle into the upper part of the shroud head by connecting it with in-reactor piping at the upper part of the shroud head.

以下、本発明の実施例を図によって説明する。Embodiments of the present invention will be described below with reference to the drawings.

第1図Fi1次冷却水循濃ポンプ内蔵槃原子炉の概念図
を示す。第2図は第1図の縦断面詳細図を示す。
Figure 1 shows a conceptual diagram of the Katsu reactor with a built-in Fi primary cooling water circulation pump. FIG. 2 shows a detailed longitudinal cross-sectional view of FIG. 1.

@2図において、非常時に非常用炉心冷却水をシュラウ
ド2内の燃料集合体8の上方から散布冷却する九めの非
常用炉心スプレー10が、シュラウドヘッド6に固足さ
れ、非常用炉心冷却水ノズル11と、スリップジヨイン
ト12によって結合される曲がり炉内配管13と連結す
る。
In Fig. 2, the ninth emergency core spray 10, which sprays and cools the emergency core cooling water from above the fuel assembly 8 in the shroud 2 in the event of an emergency, is fixed to the shroud head 6, and the emergency core cooling water is sprayed from above. The nozzle 11 is connected to a bent furnace pipe 13 which is connected by a slip joint 12 .

非常用炉心冷却系は上記の如く、直接燃料集合体の上部
から散水冷却する方式の他、配管破断により流出した冷
却材を補い、炉心部を水清けするための注水系がめる。
As mentioned above, the emergency core cooling system includes a water injection system that directly sprays water from the top of the fuel assembly, as well as a water injection system to supplement the coolant that has flowed out due to pipe rupture and to clean the core.

この注水系は、従来、特願55−164274において
は、原子炉圧力容器ノズルより、纂1図に示すダウンカ
マ部Aに注水され、この部分を降下し、下部プレナムB
t経て炉心部Ct冷却するよう設計されていた。しかし
この場合、注入された冷水が高温の原子炉圧力容器壁に
直接当り、熱衝撃により容器の健全性を損う恐れがある
Conventionally, this water injection system has been proposed in Japanese Patent Application No. 55-164274, in which water is injected from a reactor pressure vessel nozzle into the downcomer section A shown in Figure 1, descends through this section, and flows into the lower plenum B.
It was designed to cool the reactor core Ct after 100 ms. However, in this case, the injected cold water directly hits the high-temperature reactor pressure vessel wall, and there is a risk that the integrity of the vessel may be damaged due to thermal shock.

そこで本発明においては纂3図に示す如く、非常用注水
ノズル14より、ストップジヨイント15によって結合
される曲り炉内配管16tシユラウドヘツド6に取付け
、注水された非常用炉心冷却水をシュラウドヘッド上部
よりシュラウド内に注入するようにしたものである。炉
内配管の取付は位置は、上部格子板7より下方のシュラ
ウド2の部分とすると、万一非常用注水ノズル14に接
続する配管が破断した場合サイフオン効果により、シュ
ラウド内の水位が下がってしまうやれのめるため、上部
格子板7よシ上方とし、かつ炉心スプレー10の散水分
布に悪影響を及はさないよう炉水スプレーlOより上方
のシュラウドヘッド6上部としている。iた曲り炉内配
管16は、燃料交換時には、スリツブシ薗インド15で
離脱し、シュラウドヘッド6と一体で取外しが可能であ
り、燃料交換の妨けとはならない。
Therefore, in the present invention, as shown in Figure 3, the emergency water injection nozzle 14 is attached to the shroud head 6 with 16t of bent reactor piping connected by the stop joint 15, and the injected emergency core cooling water is injected from the upper part of the shroud head. It is designed to be injected into the shroud. If the in-furnace piping is installed in the part of the shroud 2 below the upper grid plate 7, if the piping connected to the emergency water injection nozzle 14 were to break, the water level in the shroud would drop due to the siphon effect. In order to avoid this problem, the shroud head 6 is placed above the upper grid plate 7, and above the reactor water spray IO so as not to adversely affect the water distribution of the core spray 10. At the time of fuel exchange, the curved furnace pipe 16 is detached from the slotted pipe 15 and can be removed together with the shroud head 6, so that it does not interfere with the fuel exchange.

本発明によれば、原子炉圧力容器の健全性を損う恐れが
なく、非常時に炉心の冷却に必要な冷却水を注水するこ
とが出来るので、原子炉の安全性信頼性を向上すること
ができる。
According to the present invention, it is possible to inject the cooling water necessary for cooling the reactor core in an emergency without risking damage to the integrity of the reactor pressure vessel, thereby improving the safety and reliability of the reactor. can.

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

第1図は1次冷却水循濃ポンプ内蔵型原子炉の概念図、
第2図は第1図の縦断面図、Jll!3図は本発明の非
常用炉心注水配管の詳細図である。 14・・・非常用炉心注水ノズル、15・・・スリップ
ジヨイント、16・・・曲シ炉内配管。
Figure 1 is a conceptual diagram of a nuclear reactor with a built-in primary cooling water circulation pump.
Figure 2 is a longitudinal sectional view of Figure 1, Jll! FIG. 3 is a detailed diagram of the emergency core water injection piping of the present invention. 14...Emergency core water injection nozzle, 15...Slip joint, 16...Curved in-core piping.

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉1次冷却水循環ポンプtm子炉圧力容器内に
内蔵した原子炉において、非常用炉心冷却水ヲ、原子炉
圧力容器ノズルよシ着脱可能なスリップジヨイント又は
ベローを有する炉内配管によ抄シュラウドヘッド上部に
注水する構造t%像とする原子炉。
1. Reactor primary cooling water circulation pump tm In a nuclear reactor built in the child reactor pressure vessel, emergency core cooling water is supplied to the reactor piping having a removable slip joint or bellows from the reactor pressure vessel nozzle. A nuclear reactor with a structural t% image of water injection into the upper part of the Yosho shroud head.
JP57063893A 1982-04-19 1982-04-19 Reactor Pending JPS58180992A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57063893A JPS58180992A (en) 1982-04-19 1982-04-19 Reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57063893A JPS58180992A (en) 1982-04-19 1982-04-19 Reactor

Publications (1)

Publication Number Publication Date
JPS58180992A true JPS58180992A (en) 1983-10-22

Family

ID=13242428

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57063893A Pending JPS58180992A (en) 1982-04-19 1982-04-19 Reactor

Country Status (1)

Country Link
JP (1) JPS58180992A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009175109A (en) * 2008-01-21 2009-08-06 Korea Atom Energ Res Inst Device and method for directly injecting emergency core cooling water into reactor vessel

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009175109A (en) * 2008-01-21 2009-08-06 Korea Atom Energ Res Inst Device and method for directly injecting emergency core cooling water into reactor vessel

Similar Documents

Publication Publication Date Title
JPH0820542B2 (en) Pressurized water reactor
JPS58180992A (en) Reactor
JP3160476B2 (en) Reactor core debris cooling system
JPS60202390A (en) Core cooling device for emergency
JPS584099U (en) Emergency cooling system for pressurized water reactors
JPS60235092A (en) Emergency core cooling device for nuclear reactor
JP3125596B2 (en) Emergency core cooling equipment for nuclear reactors
JPH01202694A (en) Emergency reactor core cooling system of nuclear reactor
JPH0483198A (en) Emergency core cooling device of natural circulation furnace
JPS59133487A (en) Incore structure for liquid metal cooled type fast breeder
JPS62218891A (en) Double tank type fast breeder reactor
JPS5820960Y2 (en) Reactor
JPS6132637B2 (en)
JPS5862592A (en) Steam drum spray cooling device
JPS6055292A (en) Fuel aggregate
JPS58132694A (en) Reactor
JPS6022691A (en) Boiling-water type reactor
JPS60154190A (en) Fast breeder reactor
JPS587594A (en) Reactor core structure
JPS58143294A (en) Reactor core structure
JPS59117997U (en) Emergency core cooling system for boiling water reactors
JPS58100782A (en) Reactor container
JPS59150374A (en) Thermal shield device in fast breeder
JPS6110792A (en) Nuclear reactor
JPS6186674A (en) Fast breeder reactor