JPH01176988A - Reactor container - Google Patents
Reactor containerInfo
- Publication number
- JPH01176988A JPH01176988A JP63000014A JP1488A JPH01176988A JP H01176988 A JPH01176988 A JP H01176988A JP 63000014 A JP63000014 A JP 63000014A JP 1488 A JP1488 A JP 1488A JP H01176988 A JPH01176988 A JP H01176988A
- Authority
- JP
- Japan
- Prior art keywords
- containment vessel
- reactor
- water
- container
- spray
- 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
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 33
- 239000007921 spray Substances 0.000 claims abstract description 17
- 238000005507 spraying Methods 0.000 claims abstract 2
- 238000010586 diagram Methods 0.000 description 5
- 238000001816 cooling Methods 0.000 description 4
- 239000000498 cooling water Substances 0.000 description 3
- 230000001629 suppression Effects 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000001035 drying Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005188 flotation Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 230000006903 response to temperature Effects 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 239000013535 sea water Substances 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は中小炉や固有安全炉、浮揚入炉の格納容器に係
り、とりわけ、外部からの注水により格納容器の上部を
冷却して平常運転時および事故時の格納容器からの除熱
を行なうことができる水冷型の原子炉格納容器に係る。[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) The present invention relates to a containment vessel for a small to medium-sized reactor, an inherent safety reactor, or a flotation reactor. This invention relates to a water-cooled reactor containment vessel that can be cooled to remove heat from the containment vessel during normal operation and during accidents.
（従来の技術）
従来の原子炉格納容器の冷却技術について従来の沸騰水
型原子炉（以下ＢＷＲと略称する）を例にとって説明す
る。(Prior Art) A conventional cooling technology for a reactor containment vessel will be explained using a conventional boiling water reactor (hereinafter abbreviated as BWR) as an example.
第３図は従来のＢＷＲの格納容器の冷却系の主要構率機
器を示す概略図である。原子炉１及び１次系の高圧配管
を収納した原子炉格納容器２はダイアフラムフロアで上
下に支切られている。格納容器内の上部をドライウェル
４、下部をウェットウェル５と呼び、ウェットウェル内
にはサプレッションプール６が設けられており、多量の
冷却水を保有している。FIG. 3 is a schematic diagram showing the main components of the cooling system of the containment vessel of a conventional BWR. A reactor containment vessel 2 that houses the reactor 1 and the high pressure piping of the primary system is divided into upper and lower parts by a diaphragm floor. The upper part of the containment vessel is called a dry well 4, and the lower part is called a wet well 5. A suppression pool 6 is provided in the wet well and holds a large amount of cooling water.
平常運転時にドライウェルクーラフによって格納容器内
が冷却されている。また、冷却材喪失事故（ＬＯＣＡ）
などのように、原子炉１次系の高圧配管が破断して冷却
材がドライウェル内の噴出した場合は、ベント管８を通
して、サプレッションプール６内に導かれ、冷水により
凝縮される。また。During normal operation, the inside of the containment vessel is cooled by the dry well cooler. In addition, loss of coolant accident (LOCA)
When the high-pressure piping of the reactor primary system breaks and the coolant spouts out in the dry well, it is led into the suppression pool 6 through the vent pipe 8 and condensed with cold water. Also.
それと共に非常用ディーゼル発電機９を動力源とする低
圧注水ポンプ１０によって、格納容器スプレィ１１が作
動し、ドライウェル内の蒸気が凝縮冷却される。サプレ
ッションプール６の水温は原子炉１から非常用炉心冷却
水によってドライウェル内へ放出される崩壊熱により次
第に上昇する。このため海水との熱交換を行なう熱交換
器１２により冷却しつつ低圧注水ポンプにて格納容器ス
プレィを行なう。At the same time, the containment vessel spray 11 is operated by the low-pressure water injection pump 10 powered by the emergency diesel generator 9, and the steam in the dry well is condensed and cooled. The water temperature in the suppression pool 6 gradually rises due to decay heat released from the reactor 1 into the dry well by emergency core cooling water. For this reason, the containment vessel is sprayed with a low-pressure water injection pump while being cooled by a heat exchanger 12 that exchanges heat with seawater.
（発明が解決しようとする問題点）
しかし、格納容器を貫通する配管は事故時には放射性物
質を環境中へ放散しないように弁によってかく離される
可能性があるため、サプレッション＆
ンプールの水、〆上昇が止まらず、沸騰し格納容器の内
圧が設計値を超える場合が起こり得ないとは言えなかっ
た。また、ドライウェルクーラーも冷却水系がかく離さ
れるため、事故時の冷却には使えない。(Problem to be solved by the invention) However, in the event of an accident, the piping that penetrates the containment vessel may be separated by a valve to prevent the release of radioactive materials into the environment. It could not be said that there was a possibility that the internal pressure of the containment vessel would exceed the design value due to boiling without stopping. Additionally, dry well coolers cannot be used for cooling in the event of an accident because the cooling water system is separated.
本発明は上記の点に鑑み、事故時にもがく離されない格
納容器の除熱システムを提供することを目的とする。In view of the above-mentioned points, it is an object of the present invention to provide a heat removal system for a containment vessel that will not be separated even in the event of an accident.
（問題点を解決するための手段）
本発明は、格納容器の除熱手段として、格納容器下部を
水沈させるとともに上部からスプレィ水を散布させるこ
とを特徴としている。(Means for Solving the Problems) The present invention is characterized in that, as heat removal means for the containment vessel, the lower part of the containment vessel is submerged in water and spray water is sprayed from the upper part.
（作 用）
格納容器外壁をスプレィ水が流れ落ちることにより冷却
されるため、事故時においての格納容器内に充満する蒸
気が凝縮冷却される。また平常運転時においても格納容
器内の冷却ができるのでドライウェルクーラと同様の作
用も兼ねることができる。(Function) Since the spray water flows down the outer wall of the containment vessel to cool it down, the steam filling the containment vessel at the time of an accident is condensed and cooled. Furthermore, since the inside of the containment vessel can be cooled even during normal operation, it can also serve the same function as a dry well cooler.
（実施例） 以下図面を参照して本発明の実施例について説明する。(Example) Embodiments of the present invention will be described below with reference to the drawings.
第１図は本発明による原子炉格納容器の実施例を示す図
である。原子炉２１と一次系の高圧配管を収納した原子
炉格納容器２２の外周に堀を設は水源プール２３を確保
する。この水源プール２３は無限水源である海２４と連
通しており、水源プール２３の水温上昇や枯渇の心配は
ない。水源プール２３より揚水ポンプ２５によって扱み
上げられた水は格納容器上方に取付けたリングヘッダ２
６を介してスプレィノズル２７より散布され格納容器外
壁を通り落ちる。その流水による熱伝達によって格納容
器を除熱する。格納容器を冷却した水は、水源プール２
３にもどるしくみになっている。又定常運転時において
は、格納容器内の数箇所に温度計２８と圧力計２９が設
けられておりその信号出力によ−って流調弁３０の開度
を決めスプレィ量をコントロール出来るようにする６１
（他の実施例）
第２図は本発明による原子炉格納容器の他の実施例を示
す図である。第１図と異なるのは、原子炉格納容器２２
より高所にスプレィタンク３１を配置し、あらかじめ揚
水ポンプ２５もしくは雨水などによってスプレィタンク
３１に水を充満させ、原子炉格納容器内の温度変化もし
くは、圧力変化に反応して機械的に動作するバルブ３２
（例水洗トイレの水蓄めタンクのようにフロートの変化
によって適当な水位が確保されるまで給水を行なう機構
）の開閉によって、適切なスプレィ水を供給することが
可能となる。FIG. 1 is a diagram showing an embodiment of a nuclear reactor containment vessel according to the present invention. A moat is provided around the outer periphery of the reactor containment vessel 22 that houses the reactor 21 and the high pressure piping of the primary system to secure a water source pool 23. This water source pool 23 is connected to the ocean 24, which is an infinite water source, so there is no worry about the water temperature rising or drying up in the water source pool 23. The water lifted up from the water source pool 23 by the pump 25 is transferred to the ring header 2 installed above the containment vessel.
6 from the spray nozzle 27 and falls through the outer wall of the containment vessel. Heat is removed from the containment vessel through heat transfer by the flowing water. The water that cooled the containment vessel is transferred to water source pool 2.
There is a mechanism to return to 3. Also, during steady operation, thermometers 28 and pressure gauges 29 are installed at several locations inside the containment vessel, and their signal output determines the opening degree of the flow control valve 30 so that the amount of spray can be controlled. 61 (Other Embodiments) FIG. 2 is a diagram showing another embodiment of the reactor containment vessel according to the present invention. What is different from Figure 1 is the reactor containment vessel 22.
The spray tank 31 is placed at a higher location, and the spray tank 31 is filled with water using the water pump 25 or rainwater in advance, and a valve is operated mechanically in response to temperature changes or pressure changes in the reactor containment vessel. 32
(For example, a mechanism that supplies water until an appropriate water level is secured by changing the float, such as a water storage tank in a flush toilet) By opening and closing the system, it is possible to supply appropriate spray water.
本発明によれば、事故時の原子炉格納容器の内部温度、
圧力の変化に反応して自動的にスプレィ装置が働き格納
容器を除熱する。According to the present invention, the internal temperature of the reactor containment vessel at the time of an accident,
The spray system automatically operates in response to pressure changes to remove heat from the containment vessel.
また、これらの装置は全て格納容器外に配置されている
のでメンテナンスも容易にでき、スプレィの作動原理も
簡単で、コスト上も有利である。In addition, since all of these devices are located outside the containment vessel, maintenance is easy, the principle of operation of the spray is simple, and it is advantageous in terms of cost.
第１図は１本発明による原子炉格納容器の実施例、第２
図は、他の実施例を示す図、第３図、従来の原子炉格納
容器冷却系の主要構成機器を示す概略図である。
２１・・・原子炉 ２２・・・原子炉格納容
器２３・・・水源プール ２４・・・海２５・・
・揚水ポンプ ２６・・・リングヘッダ２８・・
・温度計 ２９・・・圧力計３０・・・流調
弁 ３１・・・スプレィタンク３２・・・バ
ルブ
代理人 弁理士 則 近 憲 佑
同 第子丸 健
第１図
第２図
第３図Figure 1 shows an embodiment of the reactor containment vessel according to the present invention, and Figure 2 shows an embodiment of the reactor containment vessel according to the present invention.
The figures are a diagram showing another embodiment, FIG. 3, and a schematic diagram showing main components of a conventional reactor containment cooling system. 21... Nuclear reactor 22... Reactor containment vessel 23... Water source pool 24... Sea 25...
・Lifting pump 26...Ring header 28...
・Thermometer 29...Pressure gauge 30...Flow control valve 31...Spray tank 32...Valve agent Patent attorney Nori Chika Ken Yudo Daishimaru Ken Figure 1 Figure 2 Figure 3
Claims (4)
して格納容器内を冷却することを特徴とする原子炉格納
容器。(1) A reactor containment vessel characterized in that the inside of the containment vessel is cooled by spraying water onto the outer wall of the reactor containment vessel from above.
するとともに前記格納容器の下方を冷却することを特徴
とする特許請求の範囲第１項に記載の原子炉格納容器。(2) The reactor containment vessel according to claim 1, characterized in that a moat is provided around the outer periphery of the containment vessel to serve as a spray water source and to cool the lower part of the containment vessel.
の落差を利用して前記格納容器にスプレイをすることが
できることを特徴とする特許請求の範囲第一項ないし第
二項に記載の原子炉格納容器。(3) The atom according to claim 1 or 2, characterized in that a water source is provided at a higher position than the reactor containment vessel and the water source can be used to spray the containment vessel by using its head. Reactor containment vessel.
レイ量をコントロールする機構を備えた特許請求の範囲
第一項ないし第３項記載の原子炉格納容器。(4) The reactor containment vessel according to any one of claims 1 to 3, further comprising a mechanism for controlling the spray amount based on changes in the temperature and pressure inside the reactor containment vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63000014A JPH01176988A (en) | 1988-01-04 | 1988-01-04 | Reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63000014A JPH01176988A (en) | 1988-01-04 | 1988-01-04 | Reactor container |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01176988A true JPH01176988A (en) | 1989-07-13 |
Family
ID=11462584
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63000014A Pending JPH01176988A (en) | 1988-01-04 | 1988-01-04 | Reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01176988A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ITTO20110763A1 (en) * | 2011-08-11 | 2013-02-12 | Marcopolo Engineering S P A Sistem I Ecologici | SYSTEM FOR CATCHING AND / OR ABATEMENT OF HARMFUL EMISSIONS IN AN ATMOSPHERE FROM A SYSTEM IN THE EVENT OF AN ACCIDENT, PARTICULARLY A NUCLEAR SYSTEM |
| JP2015031684A (en) * | 2013-08-07 | 2015-02-16 | 株式会社東芝 | Nuclear power plant |
| CN104934078A (en) * | 2015-05-11 | 2015-09-23 | 中国核电工程有限公司 | Passive containment cooling system keeping dynamic circulation of cooling water |
| CN105697773A (en) * | 2016-03-09 | 2016-06-22 | 无锡锡洲封头制造有限公司 | Seal with drip cooling cover |
-
1988
- 1988-01-04 JP JP63000014A patent/JPH01176988A/en active Pending
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ITTO20110763A1 (en) * | 2011-08-11 | 2013-02-12 | Marcopolo Engineering S P A Sistem I Ecologici | SYSTEM FOR CATCHING AND / OR ABATEMENT OF HARMFUL EMISSIONS IN AN ATMOSPHERE FROM A SYSTEM IN THE EVENT OF AN ACCIDENT, PARTICULARLY A NUCLEAR SYSTEM |
| WO2013021308A1 (en) * | 2011-08-11 | 2013-02-14 | Marcopolo Engineering S.P.A. Sistemi Ecologici | System for abatement of noxious emissions in the atmosphere from an industrial or nuclear power plant |
| CN103999163A (en) * | 2011-08-11 | 2014-08-20 | 马可波罗工程有限公司系统生态部 | system for abatement of noxious emissions in the atmosphere from an industrial or nuclear power plant |
| JP2015031684A (en) * | 2013-08-07 | 2015-02-16 | 株式会社東芝 | Nuclear power plant |
| CN104934078A (en) * | 2015-05-11 | 2015-09-23 | 中国核电工程有限公司 | Passive containment cooling system keeping dynamic circulation of cooling water |
| CN105697773A (en) * | 2016-03-09 | 2016-06-22 | 无锡锡洲封头制造有限公司 | Seal with drip cooling cover |
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