JPH0295299A - Nuclear reactor containment - Google Patents

Nuclear reactor containment

Info

Publication number
JPH0295299A
JPH0295299A JP63246956A JP24695688A JPH0295299A JP H0295299 A JPH0295299 A JP H0295299A JP 63246956 A JP63246956 A JP 63246956A JP 24695688 A JP24695688 A JP 24695688A JP H0295299 A JPH0295299 A JP H0295299A
Authority
JP
Japan
Prior art keywords
containment vessel
outer peripheral
pool
containment
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
JP63246956A
Other languages
Japanese (ja)
Inventor
Sunao Narabayashi
直 奈良林
Hideaki Takahashi
秀明 高橋
Noboru Saito
登 斎藤
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
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP63246956A priority Critical patent/JPH0295299A/en
Publication of JPH0295299A publication Critical patent/JPH0295299A/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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To speedily and stably cool the containment for a long period after a cooling material losing accident by consisting an outer peripheral containment pool of small-sized section outer peripheral containment pools. CONSTITUTION:The outer peripheral containment pool 48 consists of the small- sized section outer peripheral containment pools 49 which are arranged in the height direction and circumferential direction of the external wall of the containment 46 and the water in an upper water supplement pool 50 is supplied to the section outer peripheral pools 49 through water supplement pipe 51, water supplement branching pipes 52, and a float valve 53 to secure a constant pool water level 54. Further, the section outer peripheral pools 49 are open to the air through an atmospheric vent pipe 55 and the water temperature of the section outer peripheral pools 49 is limited to 100-110 deg.C. Then, heat generated in the containment 46 is conducted to the wall of the containment 46 and further conducted to the water in the outer peripheral pool 48. In the outer peripheral pool 48, a natural circulation flow is generated and boiling is caused in the internal wall of the pool to cool the containment 46 with the boiling latent heat.

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、沸騰水型原子炉(以下BWRと称す)の原子
炉格納容器に係り、特に冷却材喪失事故時の格納容器冷
却構造の改良に関する。
[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a reactor containment vessel for a boiling water reactor (hereinafter referred to as BWR), and in particular to a reactor containment vessel in the event of a loss of coolant accident. Concerning improvement of container cooling structure.

(従来の技術) 第9図は、従来のBWRにおける原子炉格納容器の冷却
系主要構成機器を示す概略図である。原子炉圧力容器1
および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3で上下に仕切られている。格納
容器2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5内には、圧力抑制室6が
設けられており、多量の冷却水を保有している。平常運
転時は、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。冷却材喪失事故(LOCA)等のように
、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4内に噴出した場合は、ベント管8を通じて圧力抑
制室6内に導かれ、冷却水により凝縮される。また、そ
れとともに非常用ディーゼル発電機を動力源とする低圧
給水ポンプ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。圧力抑制室
6の水温は原子炉1から非常用炉心冷却水により、ドラ
イウェル4内へ放出される崩壊熱によって次第に上昇す
る。このため海水との熱交換を行う熱交換器12により
冷却しつつ低圧ポンプにより格納容器スプレィ11を行
う。
(Prior Art) FIG. 9 is a schematic diagram showing main components of a cooling system of a reactor containment vessel in a conventional BWR. Reactor pressure vessel 1
A reactor containment vessel 2 that houses high-pressure piping for the primary system is divided into upper and lower parts by a diaphragm floor 3. The upper part of the containment vessel 2 is called a dry well 4, and the lower part is called a wet well 5. A pressure suppression chamber 6 is provided in the wet well 5 and holds a large amount of cooling water. During normal operation, the inside of the containment vessel is cooled by the dry well cooler. When the high pressure piping of the reactor primary system ruptures and coolant spouts into the dry well 4, such as in a loss of coolant accident (LOCA), the coolant is guided into the pressure suppression chamber 6 through the vent pipe 8, Condensed by cooling water. At the same time, the containment vessel spray 11 is operated by the low-pressure water supply pump 10 powered by the emergency diesel generator, and the steam in the dry well is condensed and cooled. The water temperature in the pressure suppression chamber 6 gradually rises due to decay heat released into the dry well 4 by emergency core cooling water from the reactor 1. For this reason, the containment vessel spray 11 is performed using a low-pressure pump while being cooled by a heat exchanger 12 that exchanges heat with seawater.

以上の構成を有する従来の原子炉格納容器において、L
OCA時にドライウェル4や圧力抑制室6の水を冷却す
るためには、低圧給水ポンプ10や熱交換器12等の動
的機器が正常に作動することが必須条件である。この必
須条件の制約を除き、しかもより確実な冷却手段が試み
られている。例えば特開昭63−75594号公報に示
されているように、原子炉圧力容器を格納する格納容器
の外周部に格納容器外周ブールを設け、この格納容器外
周プール内の水の昇温および蒸発により、前記格納容器
を冷却するようにした自然放熱型の原子炉格納容器が提
案されている。第10図および第11図は、従来のこの
種の原子炉格納容器をそれぞれ示す。
In the conventional reactor containment vessel having the above configuration, L
In order to cool the water in the dry well 4 and the pressure suppression chamber 6 during OCA, it is essential that dynamic equipment such as the low-pressure water pump 10 and the heat exchanger 12 operate normally. Attempts have been made to develop more reliable cooling methods that eliminate this constraint. For example, as shown in Japanese Unexamined Patent Publication No. 63-75594, a containment vessel outer circumference boule is provided on the outer circumference of the containment vessel that houses the reactor pressure vessel, and water in the containment vessel outer circumferential pool is heated and evaporated. Accordingly, a natural heat dissipation type reactor containment vessel in which the containment vessel is cooled has been proposed. FIGS. 10 and 11 respectively show conventional reactor containment vessels of this type.

すなわち、第10図に示す従来の原子炉格納容器は、炉
心21を内蔵する原子炉圧力容器22を格納するドライ
ウェル23と、圧力抑制プール24を有するウェットウ
ェル25とから格納容器容器26を構成するとともに、
これら両ウェル23.25を蒸気ベント管27を介して
連通させ、かつ格納容器26の外周部に、格納容器外周
ブール28を設けるとともに、この格納容器外周ブール
28を、フロート弁29を介し上部補水ブール30に接
続し、さらに格納容器外周ブール28内を、大気ベント
管31を介し大気開放して構成されている。
In other words, in the conventional reactor containment vessel shown in FIG. At the same time,
These two wells 23 and 25 are communicated via a steam vent pipe 27, and a containment vessel outer circumference boule 28 is provided on the outer circumference of the containment vessel 26, and this containment vessel outer circumference boule 28 is connected via a float valve 29 to provide upper water supply. It is connected to the boule 30, and the inside of the containment vessel outer circumferential boule 28 is opened to the atmosphere via an atmospheric vent pipe 31.

また、第11図に示す従来の原子炉格納容器は、第10
図に示す原子炉格納容器の構成に加え、格納容器外周ブ
ール28に面した格納容器26の外壁に、水平方向に伝
熱板32を取付けて構成されている。
Furthermore, the conventional reactor containment vessel shown in FIG.
In addition to the configuration of the reactor containment vessel shown in the figure, a heat transfer plate 32 is attached horizontally to the outer wall of the containment vessel 26 facing the containment vessel outer peripheral boule 28.

(発明が解決しようとする課題) 第10図に示す従来の原子炉格納容器において、格納容
器外周ブール28は、第12図に示すように、幅Wが1
m以下で、高さHが10〜30mにもなって幅Wに比較
して高さHが高い形状になるため、自然対流が不十分と
なり、しかも下部の方が水頭により飽和温度が高くなる
(Problems to be Solved by the Invention) In the conventional reactor containment vessel shown in FIG. 10, the containment vessel outer perimeter boule 28 has a width W of 1 as shown in FIG.
m or less, the height H becomes 10 to 30 m, resulting in a shape where the height H is higher than the width W, resulting in insufficient natural convection, and the saturation temperature is higher at the bottom due to the water head. .

このため、温度の高い水が上昇とともに減圧沸騰して突
沸し、ガイセリングと呼ばれる不安定流動が生じ易くな
る。また、従来の格納容器外周ブール28は、周方向に
仕切りがないため周方向の渦が生じ、自然対流が阻害さ
れ易いという問題もある。このため、安定な冷却作用が
得られないという問題がある。
For this reason, as the water rises, the high temperature water boils under reduced pressure and bumps, which tends to cause unstable flow called Geisering. Further, the conventional containment vessel outer circumferential boule 28 has a problem in that, since there is no partition in the circumferential direction, vortices occur in the circumferential direction and natural convection is likely to be inhibited. Therefore, there is a problem that a stable cooling effect cannot be obtained.

また、第11図に示す従来の原子炉格納容器において、
格納容器外周ブール28内の水は、熱伝達により蒸発し
て気泡が発生するが、伝熱板32が水平方向に取付けら
れているため、伝熱板32の下部に気泡が停滞し、伝熱
効率の悪い気相ができてしまうという問題がある。また
、伝熱板32により自然対流が阻害されるため、冷却効
率が上がらないという問題もある。
Furthermore, in the conventional reactor containment vessel shown in FIG.
Water in the containment vessel outer circumferential boule 28 evaporates due to heat transfer and bubbles are generated, but since the heat transfer plate 32 is installed horizontally, the bubbles stagnate at the bottom of the heat transfer plate 32, reducing heat transfer efficiency. There is a problem that a bad gas phase is created. Furthermore, since natural convection is obstructed by the heat exchanger plate 32, there is also the problem that cooling efficiency cannot be improved.

本発明は、このような点を考慮してなされたもので、冷
却材喪失事故後、迅速かつ安定して長期に亘って格納容
器を冷却することができる原子炉格納容器を提供するこ
とを目的とする。
The present invention has been made in consideration of these points, and an object of the present invention is to provide a reactor containment vessel that can quickly and stably cool the containment vessel for a long period of time after a loss of coolant accident. shall be.

〔発明の構成〕[Structure of the invention]

(課題を解決するための手段) 本発明の第1の発明は、前記目的を達成する手段として
、原子炉格納容器を格納する格納容器の外周部に格納容
器外周ブールを設け、この格納容器外層プール内の水の
昇温および蒸発により、前記格納容器を冷却する自然放
熱型の原子炉格納容器において、前記格納容器外周プー
ルを、格納容器外壁の高さ方向および周方向にそれぞれ
複数配した小型の区分格納容器外周プールで構成するよ
うにしたことを特徴とする。
(Means for Solving the Problems) As a means for achieving the above object, the first invention of the present invention provides a containment vessel outer periphery boule on the outer periphery of the containment vessel that stores the reactor containment vessel, and this containment vessel outer layer. In a natural heat dissipation type reactor containment vessel in which the containment vessel is cooled by temperature rise and evaporation of water in the pool, a plurality of the containment vessel outer peripheral pools are arranged in a height direction and a circumferential direction of the outer wall of the containment vessel, respectively. It is characterized by being configured with a separate containment vessel and a peripheral pool.

また、本発明の第2の発明は、前記目的を達成する手段
として、前記と同様の原子炉格納容器において、格納容
器外周プールに、その内部を径方向および周方向に複数
の小室に区分する壁を設けるようにしたことを特徴とす
る。
Further, as a means for achieving the above object, a second aspect of the present invention provides, in a reactor containment vessel similar to the above, the inside of the containment vessel is divided into a plurality of small chambers in a radial direction and a circumferential direction in a peripheral pool of the containment vessel. It is characterized by having a wall.

さらに、本発明の第3の発明は、前記目的を達成する手
段として、前記同様の原子炉格納容器において、格納容
器外周プールに面した格納容器の内壁および外壁に、垂
直方向に伝熱板を設けるようにしたことを特徴とする。
Furthermore, a third invention of the present invention provides, as a means for achieving the above-mentioned object, heat transfer plates are vertically installed on the inner and outer walls of the containment vessel facing the containment vessel outer peripheral pool in the reactor containment vessel similar to the above-mentioned reactor containment vessel. It is characterized in that it is provided.

(作 用) 本発明の第1の発明に係る原子炉格納容器においては、
格納容器外周プールが複数の小型の区分格納容器外周プ
ールで構成される。このため、各区分格納容器外周プー
ルの高さを低くすることができ、水頭による飽和温度差
が小さくなって、ガイセリングを防止することが可能と
なるとともに、伝熱効率の向上も可能となる。また区分
格納容器外周プールを、ドライウェルの外壁にも設置で
きるため、大きな除熱量が得られる。
(Function) In the reactor containment vessel according to the first invention of the present invention,
The containment vessel outer circumferential pool is composed of a plurality of small sectional containment vessel outer circumferential pools. Therefore, the height of the outer circumferential pool of each divided containment vessel can be lowered, and the saturation temperature difference due to the water head is reduced, making it possible to prevent Geisering and improving heat transfer efficiency. In addition, a large amount of heat removal can be achieved because the peripheral pool of the divided containment vessel can also be installed on the outer wall of the dry well.

また、本発明の第2の発明に係る原子炉格納容器におい
ては、格納容器外周プール内が、壁により径方向および
周方向に複数の小室に区分されるため、格納容器内での
発熱が不均一になっても、格納容器外周プール内の水の
特に周方向に向かう自然循環流水が防止され、鉛直方向
の自然循環および沸騰が促進される。このため、冷却の
信頼性を向上させることが可能となる。さらに、本発明
の第3の発明に係る原子炉格納容器においては、格納容
器内の発熱が、格納容器内壁に設けられた伝熱板を介し
格納容器壁に伝えられ、さらに格納容器外壁に設けられ
た伝熱板を介し格納容器外周プール内の水に伝えられる
。格納容器外周プール内では、内周側が上昇流、外周側
が下降流となる自然循環流が発生するが、伝熱板が垂直
方向に設けられているので、この自然循環流を妨げるこ
となく冷却できるとともに、蒸発で発生した気泡を伝熱
板により停滞させることがなく、シかも伝熱板が、周方
向の自然循環流に対して邪魔板として機能する。このた
め、高効率の熱伝達が可能となる。
Furthermore, in the reactor containment vessel according to the second aspect of the present invention, the inside of the outer peripheral pool of the containment vessel is divided into a plurality of small chambers in the radial and circumferential directions by walls, so that heat generation within the containment vessel is prevented. Even if the water becomes uniform, natural circulation of water in the outer circumferential pool of the containment vessel, particularly in the circumferential direction, is prevented, and natural circulation and boiling in the vertical direction are promoted. Therefore, it becomes possible to improve the reliability of cooling. Furthermore, in the reactor containment vessel according to the third aspect of the present invention, heat generation within the containment vessel is transmitted to the containment vessel wall via a heat transfer plate provided on the inner wall of the containment vessel. The heat is transmitted to the water in the outer circumferential pool of the containment vessel through the heat exchanger plate. In the outer pool of the containment vessel, a natural circulation flow occurs with an upward flow on the inner circumference side and a downward flow on the outer circumference side, but since the heat exchanger plate is installed vertically, it can be cooled without interfering with this natural circulation flow. At the same time, the bubbles generated by evaporation are not stagnated by the heat exchanger plate, and the heat exchanger plate also functions as a baffle plate against the natural circulation flow in the circumferential direction. Therefore, highly efficient heat transfer is possible.

(実施例) 以下、本発明の第1実施例を第1図ないし第5図を参照
して説明する。
(Example) Hereinafter, a first example of the present invention will be described with reference to FIGS. 1 to 5.

第1図において、符号41は炉心42を内蔵する原子炉
圧力容器であり、この原子炉圧力容器41は、ドライウ
ェル43内に格納され、このドライウェル43は、圧力
抑制プール44を有するウェットウェル45とともに格
納容器46を構成している。そして、ドライウェル43
とウェットウェル45とは、蒸気ベント管47を介して
連結されており、また格納容器46の外周部には、冷却
材喪失事故後の格納容器46の冷却を行なう格納容器外
周プール48が設けられている。
In FIG. 1, reference numeral 41 denotes a reactor pressure vessel containing a reactor core 42. This reactor pressure vessel 41 is housed in a dry well 43, and this dry well 43 is a wet well having a pressure suppression pool 44. Together with 45, it constitutes a containment vessel 46. And Drywell 43
and the wet well 45 are connected via a steam vent pipe 47, and a containment vessel outer peripheral pool 48 is provided at the outer periphery of the containment vessel 46 to cool the containment vessel 46 after a coolant loss accident. ing.

格納容器外周プール48は、第1図および第2図に示す
ように格納容器46外壁の高さ方向および周方向にそれ
ぞれ複数配した小型の区分格納容器外周プール49で構
成されており、各区分格納容器外周プール49には、上
部補水プール50内の水が補水配管51、補水枝管52
およびフロート弁53を介してそれぞれ供給され、一定
水位のプール水面54が確保されるようになっている。
As shown in FIGS. 1 and 2, the containment vessel outer peripheral pool 48 is composed of a plurality of small sectional containment vessel outer periphery pools 49 arranged in the height direction and circumferential direction of the outer wall of the containment vessel 46, respectively. The water in the upper replenishment pool 50 is transferred to the outer peripheral pool 49 of the containment vessel through a replenishment pipe 51 and a replenishment branch pipe 52.
and a float valve 53, respectively, to ensure a pool water surface 54 at a constant water level.

また、各区分格納容器外周プール49は、第1図に示す
ように大気ベント管55を介して大気開放され、各区分
格納容器外周プール4つ内の水温が100℃〜110℃
に制限できるようになっている。
In addition, the outer peripheral pools 49 of each divided containment vessel are opened to the atmosphere through the atmospheric vent pipe 55 as shown in FIG.
It is now possible to limit

次に、本実施例の作用について説明する。Next, the operation of this embodiment will be explained.

格納容器46での発熱は、格納容器46の壁に伝えられ
、さらに格納容器外周プール48内の水に伝えられる。
The heat generated in the containment vessel 46 is transmitted to the walls of the containment vessel 46 and further to the water in the containment vessel outer peripheral pool 48.

格納容器外周ブール48内では、自然循環流が発生し、
プール内壁で沸騰が起こり、沸騰潜熱により格納容器4
6が冷却される。
A natural circulation flow occurs within the containment vessel outer peripheral boule 48,
Boiling occurs on the inner wall of the pool, and the latent heat of boiling causes the containment vessel 4 to boil.
6 is cooled.

ところで、本実施例においては、格納容器外周ブール4
8が、複数の区分格納容器外周ブール49で構成されて
いるので、第3図に示すように各区分格納容器外周ブー
ル49の幅Wを0.5m、高さHを2〜5mに押えるこ
とができる。このため、水頭による飽和温度差を10℃
以下と小さくすることができ、ガイセリングを防止でき
る。また、除熱量に比例する部分は、第3図に符号B1
゜B 2 、・・・B1を付して示す傾斜部分であり、
これは、第12図の従来例で符号Aを付して示す斜線部
分に対応する。両図の比較からも明らかなように、 となり、除熱量を増大させることができる。
By the way, in this embodiment, the containment vessel outer perimeter boule 4
8 is composed of a plurality of divided containment vessel outer circumferential boules 49, so as shown in FIG. Can be done. Therefore, the saturation temperature difference due to water head is 10℃
It can be made as small as below, and Geisering can be prevented. In addition, the part proportional to the amount of heat removed is indicated by the symbol B1 in Fig. 3.
゜B 2 , . . . is an inclined part indicated with B1,
This corresponds to the shaded area indicated by the symbol A in the conventional example in FIG. As is clear from the comparison of both figures, the amount of heat removed can be increased.

また、各区分格納容器外周ブール49は、大気ベント管
55を介して大気開放されているので、第3図に示すよ
うに各区分格納容器外周ブール49内の水温を100〜
110℃に制限することができる。このため、第4図(
a)、(b)に示すように格納容器46の内圧が4.7
atのとき、温度は130〜150℃であり、格納容器
46の壁面内外温度差を20〜50℃と大きくとること
ができ、熱伝達も大きくできる。
In addition, since the outer circumferential boule 49 of each divided containment vessel is exposed to the atmosphere via the atmospheric vent pipe 55, the water temperature in the outer circumferential boule 49 of each divided containment vessel is 100 to 100% as shown in FIG.
The temperature can be limited to 110°C. For this reason, Figure 4 (
As shown in a) and (b), the internal pressure of the containment vessel 46 is 4.7
At the time of at, the temperature is 130 to 150°C, and the temperature difference between the inside and outside walls of the containment vessel 46 can be as large as 20 to 50°C, and heat transfer can also be increased.

また、区分格納容器外周ブール49は、ドライウェル4
3の外壁にも設置できるため、ドライウェル43からの
除熱も可能となる。これは、単に伝熱面積の増加のみな
らず、窒素分圧が低く凝縮熱伝達が高いドライウェル4
3からの大きな除熱量が、格納容器46からの除熱量に
加算されることを意味する。なぜなら、ドライウェル4
3内の窒素は、蒸気とともに蒸気ベント管47を通じて
圧力抑制ブール44に押し出され、第5図に示すように
ウェットウェル気相部の凝縮熱伝達率は、極端に低下し
ているためである。
In addition, the partitioned containment vessel outer circumferential boule 49 is connected to the dry well 4
Since it can also be installed on the outer wall of the dry well 43, it is also possible to remove heat from the dry well 43. This not only increases the heat transfer area, but also improves dry well 4, which has low nitrogen partial pressure and high condensation heat transfer.
This means that the large amount of heat removed from the container 46 is added to the amount of heat removed from the containment vessel 46. Because Drywell 4
This is because the nitrogen in the wet well gas phase is pushed out together with steam to the pressure suppression boule 44 through the steam vent pipe 47, and as shown in FIG. 5, the condensation heat transfer coefficient of the wet well gas phase is extremely reduced.

このように、格納容器外周ブール48を、複数の区分格
納容器外周ブール49で構成しているので、冷却)イ喪
失事故後の冷却を、動力や操作員の操作を要せず、長期
に亘って安定させることができる。また、格納容器46
からの除熱量を大きくとれるために、格納容器46の小
型化が可能となり、原子炉建屋のコストを大幅に下げる
ことができる。
In this way, since the containment vessel outer circumferential boule 48 is composed of a plurality of divided containment vessel outer circumferential boules 49, cooling after a cooling loss accident can be performed for a long period of time without requiring power or operation by an operator. can be stabilized. In addition, the containment vessel 46
Since a large amount of heat can be removed from the reactor, the containment vessel 46 can be made smaller, and the cost of the reactor building can be significantly reduced.

第6図および・第7図は、本発明の第2実施例を示すも
ので、格納容器外周ブール48と」二部補水ブール50
とを連結し、かつ格納容器外周ブール48内を、リング
状仕切壁61および放射状仕切壁62により、上下端が
相互に連通ずる複数の小室に区分するようにしたもので
ある。
6 and 7 show a second embodiment of the present invention, in which a containment vessel perimeter boule 48 and a two-part refilling boule 50 are shown.
The inside of the containment vessel outer circumferential boule 48 is divided into a plurality of small chambers whose upper and lower ends communicate with each other by a ring-shaped partition wall 61 and a radial partition wall 62.

すなわち、格納容器外周ブール48は、第6図に示すよ
うにその上端部が上部補水ブール50の下端に連結され
て一体構造になっており、この格納容器外周ブール48
内には、第6図および第7図に示すように、リング状仕
切壁61および放射状仕切壁62がそれぞれ配置されて
いる。そしてこれにより、格納容器外周ブール48の内
部が、径方向および周方向に、上下端が連通ずる複数の
小室に区分されるようになつている。
That is, as shown in FIG. 6, the outer circumferential boule 48 of the containment vessel has an integral structure with its upper end connected to the lower end of the upper water replenishment boule 50.
Inside, as shown in FIGS. 6 and 7, a ring-shaped partition wall 61 and a radial partition wall 62 are arranged, respectively. As a result, the inside of the containment vessel outer circumferential boule 48 is divided into a plurality of small chambers whose upper and lower ends communicate with each other in the radial and circumferential directions.

なお、その他の点については、前記第1実施例と同一構
成となっている。
Note that the other points have the same configuration as the first embodiment.

次に、本実施例の作用について説明する。Next, the operation of this embodiment will be explained.

事故時には、格納容器46内の発熱が格納容器46壁に
伝えられ、さらに格納容器外周ブール48に伝えられる
。格納容器外周ブール48内では、内周側が上昇流、外
周側が下降流となる自然循環流が発生する。そして、格
納容器外周ブール48内壁で沸騰が起こり、沸騰潜熱に
より格納容器46が冷却される。
In the event of an accident, heat generated within the containment vessel 46 is transmitted to the containment vessel 46 wall and further to the containment vessel outer peripheral boule 48 . A natural circulation flow occurs within the containment vessel outer boule 48, with an upward flow on the inner circumferential side and a downward flow on the outer circumferential side. Then, boiling occurs on the inner wall of the containment vessel outer peripheral boule 48, and the containment vessel 46 is cooled by the latent heat of boiling.

ところで、格納容器46内での発熱が不均一の場合には
、格納容器外周ブール48内に、周方向に向かう自然循
環流が生じることになる。ところが、本実施例では、格
納容器外周ブール48内に、リング状仕切壁61および
放射状仕切壁62が設けられているので、特に放射状仕
切壁62により、周方向に向かう自然循環流が防止され
、鉛直方向の自然循環流および沸騰が促進される。この
ため、格納容器46の冷却効率を向上させることができ
る。
By the way, if the heat generation within the containment vessel 46 is non-uniform, a natural circulating flow in the circumferential direction will occur within the containment vessel outer peripheral boule 48. However, in this embodiment, since the ring-shaped partition wall 61 and the radial partition wall 62 are provided in the containment vessel outer peripheral boule 48, the radial partition wall 62 in particular prevents the natural circulation flow in the circumferential direction. Vertical natural circulation flow and boiling are promoted. Therefore, the cooling efficiency of the containment vessel 46 can be improved.

第8図は、本発明の第3実施例を示すもので、格納容器
外周ブール48に面した格納容器46の壁面、すなわち
格納容器46の周壁面に、内側伝熱板71および外側伝
熱板72を垂直方向にそれぞれ設けるようにしたもので
ある。
FIG. 8 shows a third embodiment of the present invention, in which inner heat exchanger plate 71 and outer heat exchanger plate 72 are provided in the vertical direction.

すなわち、格納容器46の周壁には、その内面に内側伝
熱板71が垂直方向に配されているとともに、外面に外
側伝熱板72が垂直方向に配されている。
That is, on the peripheral wall of the containment vessel 46, an inner heat transfer plate 71 is arranged vertically on the inner surface thereof, and an outer heat transfer plate 72 is arranged vertically on the outer surface.

なお、その他の点については、前記第1実施例と同一構
成となっている。
Note that the other points have the same configuration as the first embodiment.

次に、本実施例の作用について説明する。Next, the operation of this embodiment will be explained.

事故時には、格納容器46内の発熱が格納容器46内周
壁の内側伝熱板71を介し格納容器46壁に伝えられ、
さらに格納容器46外周壁の外側伝熱板72を介し格納
容器外周ブール48内の水に伝えられる。格納容器外周
プール48内では、内周側は上昇流、外周側は下降流と
なる自然循環流が発生する。そして、格納容器外周プー
ル48内壁で沸騰が起こり、沸騰潜熱により格納容器4
6が冷却される。
In the event of an accident, heat generated within the containment vessel 46 is transmitted to the walls of the containment vessel 46 via the inner heat transfer plate 71 on the inner circumferential wall of the containment vessel 46.
The heat is further transmitted to the water in the containment vessel outer peripheral boule 48 via the outer heat transfer plate 72 on the outer peripheral wall of the containment vessel 46 . In the containment vessel outer circumferential pool 48, a natural circulating flow is generated in which the inner circumferential side is an upward flow and the outer circumferential side is a downward flow. Then, boiling occurs on the inner wall of the outer peripheral pool 48 of the containment vessel, and due to the latent heat of boiling, the containment vessel 4
6 is cooled.

この際、内側伝熱板71は垂直方向に設けられているの
で、格納容器46内の自然循環流が妨げられず、格納容
器46内壁面積を実質的に増大させて熱伝達効率を向上
させることができる。また、外側伝熱板72も垂直方向
に設けられているので、格納容器46内の熱を、効率よ
く格納容器外周プール48に逃がすことができる。また
、格納容器外周ブール48内で発生する垂直方向の自然
循環流を、外側伝熱板72により妨げられることがない
とともに、周方向の自然循環流が抑制され、しかも蒸発
で発生した気泡を外側伝熱板72により停滞させること
がないため、格納容器46を迅速かつ効率よく冷却する
ことができる。
At this time, since the inner heat transfer plate 71 is provided in the vertical direction, the natural circulation flow within the containment vessel 46 is not hindered, and the inner wall area of the containment vessel 46 is substantially increased to improve heat transfer efficiency. Can be done. Further, since the outer heat transfer plate 72 is also provided in the vertical direction, the heat within the containment vessel 46 can be efficiently released to the containment vessel outer peripheral pool 48. In addition, the vertical natural circulation flow generated within the containment vessel outer circumferential boule 48 is not obstructed by the outer heat exchanger plate 72, and the circumferential natural circulation flow is suppressed. Since there is no stagnation caused by the heat transfer plate 72, the containment vessel 46 can be cooled quickly and efficiently.

〔発明の効果〕〔Effect of the invention〕

以上説明したように本発明によれば、冷却材喪失事故時
に、動力や操作員による操作を要することなく、迅速に
しかも長期に亘って安定に格納容器を冷却することがで
きる。また、格納容器からの除熱量を大きくとれるため
、格納容器を小型化でき、原子炉建屋のコストを大幅に
下げることができる。
As explained above, according to the present invention, in the event of a loss of coolant accident, the containment vessel can be cooled quickly and stably over a long period of time without requiring power or operation by an operator. Furthermore, since a large amount of heat can be removed from the containment vessel, the containment vessel can be made smaller and the cost of the reactor building can be significantly reduced.

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

第1図は本発明の第1実施例を示す原子炉格納容器の断
面図、第2図は第1図の区分格納容器外周プールの拡大
斜視図、第3図は区分格納容器外周プール内の温度分布
と伝熱量とを示す説明図、第4図(a)はウェル圧力の
変化を示すグラフ、第4図(b)はそれに対応する各部
の温度変化を示すグラフ、第5図は凝縮熱伝達率に及ぼ
す空気分圧の影響を示すグラフ、第6図は本発明の第2
実施例を示す第1図相当図、第7図は第6図の平面図、
第8図は本発明の第3実施例を示す第1図相当図、第9
図は従来の原子炉格納容器を示す断面図、第10図およ
び第11図は自然放熱型の従来の原子炉格納容器をそれ
ぞれ示す断面図、第12図は従来の格納容器外周プール
内の温度分布と伝熱量とを示す第3図相当図である。 41・・・原子炉圧力容器、43・・・ドライウェル、
44・・・圧力抑制プール、45・・・ウェットウェル
、46・・・格納容器、48・・・格納容器外周プール
、49・・・区分格納容器外周プール、55・・・大気
ベント管、61・・・リング状仕切壁、62・・・放射
状仕切壁、71・・・内側伝熱板、72・・・外側伝熱
板。
FIG. 1 is a sectional view of a reactor containment vessel showing a first embodiment of the present invention, FIG. 2 is an enlarged perspective view of the outer circumferential pool of the compartmentalized containment vessel in FIG. 1, and FIG. An explanatory diagram showing the temperature distribution and the amount of heat transfer. Fig. 4 (a) is a graph showing changes in well pressure. Fig. 4 (b) is a graph showing corresponding temperature changes in each part. Fig. 5 is a graph showing condensation heat. A graph showing the influence of air partial pressure on the transmissibility, FIG. 6 is the second embodiment of the present invention.
FIG. 1 is a diagram corresponding to the embodiment, FIG. 7 is a plan view of FIG. 6,
FIG. 8 is a diagram corresponding to FIG. 1 showing the third embodiment of the present invention, and FIG.
The figure shows a cross-sectional view of a conventional reactor containment vessel. Figures 10 and 11 are cross-sectional views of a conventional reactor containment vessel of natural heat dissipation type. Figure 12 shows the temperature inside the outer peripheral pool of a conventional containment vessel. FIG. 3 is a diagram equivalent to FIG. 3 showing the distribution and the amount of heat transfer. 41...Reactor pressure vessel, 43...Dry well,
44... Pressure suppression pool, 45... Wet well, 46... Containment vessel, 48... Containment vessel outer circumference pool, 49... Segmented containment vessel outer circumference pool, 55... Atmospheric vent pipe, 61 ...Ring-shaped partition wall, 62...Radial partition wall, 71...Inner heat exchanger plate, 72...Outer heat exchanger plate.

Claims (1)

【特許請求の範囲】 1、原子炉圧力容器を格納する格納容器の外周部に格納
容器外周プールを設け、この格納容器外周プール内の水
の昇温および蒸発により、前記格納容器を冷却する自然
放熱型の原子炉格納容器において、前記格納容器外周プ
ールを、格納容器外壁の高さ方向および周方向にそれぞ
れ複数配した小型の区分格納容器外周プールで構成した
ことを特徴とする原子炉格納容器。 2、原子炉圧力容器を格納する格納容器の外周部に格納
容器外周プールを設け、この格納容器外周プール内の水
の昇温および蒸発により、前記格納容器を冷却する自然
放熱型の原子炉格納容器において、前記格納容器の外周
プールに、その内部を径方向および周方向に複数の小室
に区分する壁を設けたことを特徴とする原子炉格納容器
。 3、原子炉圧力容器を格納する格納容器の外周部に格納
容器外周プールを設け、この格納容器外周プール内の水
の昇温および蒸発により、前記格納容器を冷却する自然
放熱型の原子炉格納容器において、前記格納容器外周プ
ールに面した格納容器の内壁および外壁に垂直方向に伝
熱板を設けたことを特徴とする原子炉格納容器。
[Claims] 1. A containment vessel outer circumference pool is provided at the outer circumference of the containment vessel that stores the reactor pressure vessel, and a natural cooling system is provided to cool the containment vessel by increasing the temperature and evaporating water in the containment vessel outer circumference pool. A reactor containment vessel of a heat dissipation type, characterized in that the containment vessel outer peripheral pool is constituted by a plurality of small sectional containment vessel outer peripheral pools arranged in a height direction and a circumferential direction of the outer wall of the containment vessel. . 2. Natural heat dissipation type reactor containment in which a containment vessel outer peripheral pool is provided on the outer periphery of the containment vessel that stores the reactor pressure vessel, and the containment vessel is cooled by temperature rise and evaporation of water in this containment vessel outer peripheral pool. A nuclear reactor containment vessel, characterized in that the outer peripheral pool of the containment vessel is provided with a wall that divides the inside thereof into a plurality of small chambers in the radial and circumferential directions. 3. Natural heat dissipation type reactor containment, in which a containment vessel outer peripheral pool is provided on the outer periphery of the containment vessel that stores the reactor pressure vessel, and the containment vessel is cooled by temperature rise and evaporation of water in this containment vessel outer peripheral pool. A nuclear reactor containment vessel, characterized in that heat transfer plates are provided vertically on the inner and outer walls of the containment vessel facing the containment vessel outer peripheral pool.
JP63246956A 1988-09-30 1988-09-30 Nuclear reactor containment Pending JPH0295299A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP63246956A JPH0295299A (en) 1988-09-30 1988-09-30 Nuclear reactor containment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP63246956A JPH0295299A (en) 1988-09-30 1988-09-30 Nuclear reactor containment

Publications (1)

Publication Number Publication Date
JPH0295299A true JPH0295299A (en) 1990-04-06

Family

ID=17156230

Family Applications (1)

Application Number Title Priority Date Filing Date
JP63246956A Pending JPH0295299A (en) 1988-09-30 1988-09-30 Nuclear reactor containment

Country Status (1)

Country Link
JP (1) JPH0295299A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2791172A1 (en) * 1999-03-17 2000-09-22 Franz Jos Urdl PROTECTION SYSTEM FOR NUCLEAR POWER PLANT
JP2016503902A (en) * 2013-01-18 2016-02-08 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Passive system for cooling reactor cores.

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2791172A1 (en) * 1999-03-17 2000-09-22 Franz Jos Urdl PROTECTION SYSTEM FOR NUCLEAR POWER PLANT
JP2016503902A (en) * 2013-01-18 2016-02-08 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Passive system for cooling reactor cores.

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