JPS59136681A - Two-chamber type reactor container - Google Patents

Two-chamber type reactor container

Info

Publication number
JPS59136681A
JPS59136681A JP58009826A JP982683A JPS59136681A JP S59136681 A JPS59136681 A JP S59136681A JP 58009826 A JP58009826 A JP 58009826A JP 982683 A JP982683 A JP 982683A JP S59136681 A JPS59136681 A JP S59136681A
Authority
JP
Japan
Prior art keywords
dry well
chamber
containment vessel
water
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
JP58009826A
Other languages
Japanese (ja)
Inventor
真田 高宥
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 JP58009826A priority Critical patent/JPS59136681A/en
Publication of JPS59136681A publication Critical patent/JPS59136681A/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

(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〕 本発明は原子炉格納容器に係シ、特に内部が上部ドライ
ウェル室と下部ドライウェル室に分れ、さらに空間部を
連絡することができ、ぼた流路を閉鎖することができる
逆止装置を具備したドライウェル連絡管を備えた原子炉
格納容器に関する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a nuclear reactor containment vessel, and in particular, the interior thereof is divided into an upper dry well chamber and a lower dry well chamber, and the spaces can be further communicated. The present invention relates to a nuclear reactor containment vessel equipped with a dry well communication pipe equipped with a check device capable of closing a slag flow path.

〔従来技術〕[Prior art]

従来の原子炉格納容器はドライウェル連絡管に逆止装置
がなく上部ドライウェルの空間部の配管破断事故時に放
射能を含む高温の原子炉水がドライウェル連絡管を通っ
て下部ドライウェルへ流入する。下部ドライウェルには
高温水を冷却する装置がなく流入水は高温で保持され、
原子炉格納容器の内圧が低下するのに長期の時間を要し
ビンボール等が原子炉格納容器壁にあった場合、放射能
が外部へ漏戊し易い状態が長期間続く欠点き有する。
In conventional reactor containment vessels, there is no check device in the dry well connecting pipe, so in the event of a pipe rupture in the upper dry well space, high-temperature reactor water containing radioactivity will flow into the lower dry well through the dry well connecting pipe. do. The lower drywell does not have a device to cool high-temperature water, so the inflow water is kept at a high temperature.
It takes a long time for the internal pressure of the reactor containment vessel to drop, and if a bottle ball or the like is found on the wall of the reactor containment vessel, there is a drawback that radioactivity tends to leak to the outside for a long period of time.

非常用炉心冷却系は圧力抑制室の貯蔵水を吸引して原子
炉に注入する。注入された水は炉心を冷却した後破断口
から流出しドライウェル内に放出されるが、圧力抑制室
に戻らず下部ドライウェルに流入した場合、圧力抑制室
の貯蔵水が減少し、水位の低下によシ非常用炉心冷却系
のポンプ押込み静水頭(NPSH)が不足すると共に貯
蔵水を冷却する熱交換器の容量が増大する欠点をMする
The emergency core cooling system sucks the water stored in the suppression chamber and injects it into the reactor. After the injected water cools the core, it flows out of the fracture port and is released into the dry well. However, if it does not return to the suppression chamber and flows into the lower dry well, the water stored in the suppression chamber will decrease and the water level will drop. As a result, the pump thrust hydrostatic head (NPSH) of the emergency core cooling system becomes insufficient and the capacity of the heat exchanger for cooling the stored water increases.

〔発明の目的〕[Purpose of the invention]

本発明はドライウェル連絡管に上部ドライウェルから下
部ドライウェルへの流れを閉止する逆上装置を設置する
ことによって高温炉水又は非常用炉心冷却ポンプによっ
て汲み出された圧力抑制室貯蔵水が下部ドライウェルに
流入するのを防ぎ、従来技術のような欠点のない原子炉
格納容器を提供するにある。
In the present invention, high-temperature reactor water or suppression chamber stored water pumped out by an emergency core cooling pump is transferred to the lower dry well by installing a reverse device in the dry well connecting pipe to close the flow from the upper dry well to the lower dry well. It is an object of the present invention to provide a reactor containment vessel that prevents water from flowing into a dry well and does not have the drawbacks of the prior art.

〔発明の概要〕[Summary of the invention]

本発明はドライウェル連絡管に逆止装置を設置すること
に特徴がある。更に本発明により配管破断事故時におけ
る原子炉格納容器内圧上昇を従来よシも低く抑える効果
がある。
The present invention is characterized in that a check device is installed in the dry well communication pipe. Furthermore, the present invention has the effect of suppressing the rise in internal pressure of the reactor containment vessel in the event of a pipe rupture accident to a lower level than in the past.

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

第1図に本発明の実施例を示す。以下第1図を使って説
明する。
FIG. 1 shows an embodiment of the present invention. This will be explained below using FIG.

原子炉1は原子炉格納容器2の内部に設置され更に原子
炉格納容器2の内部は上部ドライウェル室Aと下部ドラ
イウェル室B及び圧力抑制室Cに分れている。上部ドラ
イウェル室Aと下部ドライウェル室Bの空間はドライウ
ェル連絡管4で連絡している。また上部ドライウェル室
Aと圧力抑制室Cはベント管3で連絡しているがベント
管3の先端は圧力抑制室内の貯蔵水りの中までのばして
いる。
The reactor 1 is installed inside a reactor containment vessel 2, and the inside of the reactor containment vessel 2 is further divided into an upper dry well chamber A, a lower dry well chamber B, and a pressure suppression chamber C. The spaces of the upper dry well chamber A and the lower dry well chamber B are connected through a dry well communication pipe 4. Further, the upper dry well chamber A and the pressure suppression chamber C are connected through a vent pipe 3, and the tip of the vent pipe 3 extends into the water stored in the pressure suppression chamber.

ドライウェル連絡管4には逆上装置5を設置し上部ドラ
イウェル呈A内の配管6が破断して原子炉水が流出した
場合、逆止装置5で下部ドライウェル室Bへの流路を防
ぎ、破断口から流出した高温の原子炉水の全てを圧力抑
制室Cの貯蔵水中りへ導き冷却することによ、り原子炉
格納容器内圧上昇が小さくなるようにする。
A backflow device 5 is installed in the dry well communication pipe 4, and if the pipe 6 in the upper dry well chamber A breaks and reactor water flows out, the check device 5 closes the flow path to the lower dry well chamber B. All of the high-temperature reactor water flowing out from the rupture port is guided into the storage water of the pressure suppression chamber C and cooled, thereby minimizing the rise in the internal pressure of the reactor containment vessel.

下部ドライウェル室B内の配管6が破断した場合、流出
した高温の炉水の一部は気化して蒸気となりドライウェ
ル連絡管4を通り逆止弁5を押し開き上部ドライウェル
室Aを経由しベント管3を通って圧力抑制室Cの貯蔵水
りへ導き冷却される。
When the pipe 6 in the lower dry well chamber B breaks, a portion of the high-temperature reactor water that flows out evaporates into steam, passes through the dry well connection pipe 4, pushes the check valve 5 open, and passes through the upper dry well chamber A. The water is then led through the vent pipe 3 to the storage water tank in the pressure suppression chamber C, where it is cooled.

気化しなかった炉水は下部ドライウェル室B内に溜るが
、下部ドライウェル室B内の配管の口径は最大でも50
ミリメートル程度であり万、−破断が起っても原子炉格
納容器2の内圧上昇は小さい。
Reactor water that has not vaporized remains in the lower dry well chamber B, but the diameter of the piping in the lower dry well chamber B is at most 50 mm.
Even if a rupture occurs, the increase in the internal pressure of the reactor containment vessel 2 will be small.

逆止装置5は自重で閉鎖する一般的な逆止弁と同じ閉鎖
原理である。
The check device 5 has the same closing principle as a general check valve that closes under its own weight.

本実施例によれば上部ドライウェル室Aかと下部ドライ
ウェル室Bへの高温炉水の流入がないので従来技術の欠
点を解消できる効果がある。更に本実施例によれば配管
破断事故時における原子炉格納容器2内のピーク圧力を
低くすることができ安全性を向上できる効果がある。第
2図は上部ドライウェル室A内での最大配管破断事故時
の原子炉格納容器2の内圧変化示す図である。第2図の
曲線イは逆止装置のない場合、曲線口は逆止装置がある
場合でありこの図から本発明によって事故時の原子炉格
納容器内ピーク圧力は約25%低減できる事が判る。
According to this embodiment, there is no inflow of high-temperature reactor water into the upper dry well chamber A and the lower dry well chamber B, so that the disadvantages of the prior art can be overcome. Further, according to this embodiment, the peak pressure inside the reactor containment vessel 2 can be lowered in the event of a pipe rupture accident, and safety can be improved. FIG. 2 is a diagram showing changes in the internal pressure of the reactor containment vessel 2 at the time of the maximum pipe rupture accident in the upper dry well chamber A. Curve A in Figure 2 shows the case without a check device, and the curve at the beginning shows the case with the check device.From this figure, it can be seen that the present invention can reduce the peak pressure inside the reactor containment vessel by about 25% in the event of an accident. .

配管破断事故時の原子炉格納容器ピーク圧力はドライウ
ェル内の初期空気量に約比例する。これは配管破断事故
時の流出炉水によってドライウェル内空気が圧力抑制室
の一定空間Cへ押し込まれるためであり、空間Cの圧力
は空間A及びBの空間容積即ち空気量が多い程ピーク値
は高くなる。
The peak pressure in the reactor containment vessel at the time of a pipe rupture accident is approximately proportional to the initial amount of air in the drywell. This is because the air in the dry well is pushed into the fixed space C of the pressure suppression chamber by the reactor water that leaked out during a pipe rupture accident, and the pressure in space C increases as the space volume of spaces A and B, that is, the amount of air increases, reaches its peak value. becomes higher.

芙発明では下部ドライウェルと上部ドライウェルを逆止
装置で鎖閉するため空間Cへ押し込まれる空気量は上部
ドライウェルAの空気量だけとなり原子炉格納容器の内
圧は低くなる、 本発明の変形例・応用例は逆止装置へ遠隔駆動機構を接
続したり、構造を変えたりする等多数者えられるが全て
特許請求範囲に網羅される。
In the Fu invention, since the lower dry well and the upper dry well are closed with a check device, the amount of air pushed into the space C is only the air amount in the upper dry well A, and the internal pressure of the reactor containment vessel is lowered. Modification of the present invention There are many examples and applications, such as connecting a remote drive mechanism to the check device, changing the structure, etc., but all of them are covered by the scope of the claims.

〔発明の効果〕〔Effect of the invention〕

本発明によれば配管破断事故時における原子炉格納容器
の内圧上昇を低く抑えることができる効果がある。
According to the present invention, the increase in internal pressure of the reactor containment vessel in the event of a pipe rupture accident can be suppressed to a low level.

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

第1図は本発明の詳細な説明する図、第2図は本発明の
一つの効果を説明する図である。 l・・・原子炉、2・・・原子炉格納容器、3・・・ベ
ント管、4・・・ドライウェル連絡管、5・・・逆止装
置、6・・・配管(代表例)、7・・・配W(代表例)
、A・・・上部ドライウェル室、B・・・下部ドライウ
ェル室、C・・・圧第 1 図 ¥2 日 /       10      /l)ρ    /
りρO辛飲唆/狩川用オケラ ー嘲−bha、:
FIG. 1 is a diagram for explaining the present invention in detail, and FIG. 2 is a diagram for explaining one effect of the present invention. l... Nuclear reactor, 2... Reactor containment vessel, 3... Vent pipe, 4... Dry well communication pipe, 5... Check device, 6... Piping (representative example), 7... Distribution W (typical example)
, A...Upper dry well chamber, B...Lower dry well chamber, C...Pressure 1st figure ¥2 days/10/l)ρ/
riρOshin intoxication/Karikawa use Okeller mockery-bha,:

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉圧力容器を格納し、内部が上部ドライウェル
室と下部ドライウェル室及び底部に水を貯蔵した圧力抑
制室の各室および、上部ドライウェル室と下部ドライウ
ェル室の空間部を連絡することができ、逆止装置を具備
したドライウェル連絡管からなることを特徴とする二型
式原子炉格納容器。
1. Contains the reactor pressure vessel and connects the upper dry well chamber, lower dry well chamber, pressure suppression chamber that stores water at the bottom, and the upper dry well chamber and lower dry well chamber. A type 2 reactor containment vessel characterized by comprising a dry well communication pipe equipped with a check device.
JP58009826A 1983-01-26 1983-01-26 Two-chamber type reactor container Pending JPS59136681A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58009826A JPS59136681A (en) 1983-01-26 1983-01-26 Two-chamber type reactor container

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58009826A JPS59136681A (en) 1983-01-26 1983-01-26 Two-chamber type reactor container

Publications (1)

Publication Number Publication Date
JPS59136681A true JPS59136681A (en) 1984-08-06

Family

ID=11730935

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58009826A Pending JPS59136681A (en) 1983-01-26 1983-01-26 Two-chamber type reactor container

Country Status (1)

Country Link
JP (1) JPS59136681A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0670055U (en) * 1993-03-05 1994-09-30 秀工電子株式会社 Medal tank
JP2009145135A (en) * 2007-12-12 2009-07-02 Toshiba Corp Reactor container, and leakage-detecting floor

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0670055U (en) * 1993-03-05 1994-09-30 秀工電子株式会社 Medal tank
JP2009145135A (en) * 2007-12-12 2009-07-02 Toshiba Corp Reactor container, and leakage-detecting floor

Similar Documents

Publication Publication Date Title
US7983376B2 (en) Boiling water nuclear reactor and emergency core cooling system of the same
JPH04125495A (en) Nuclear reactor facility
US20040196948A1 (en) Integral pwr with diverse emergency cooling and method of operating same
KR890001251B1 (en) Emergency cooling device for a pressurized water nuclear reactor
JP3159820B2 (en) Reactor containment equipment
CN106328223A (en) Novel passive safety shell energy control system
CN103295654A (en) Passive safety injection system of nuclear reactor
JPH085772A (en) Reactor containment
CA1217885A (en) Means for cooling a heat-generating device
US3506539A (en) Nuclear reactors
WO2023241096A1 (en) Integrated safety system for reactor
JPS59136681A (en) Two-chamber type reactor container
JPS6238393A (en) Emergency core cooling method and device
CN202549317U (en) Passive safety injection system of nuclear reactor
JPH05142380A (en) Emergency core cooling system
CN208271569U (en) Naval reactor and its Passive residual heat removal system
JPS6375691A (en) Natural circulation type reactor
JPH05323084A (en) Reactor containment
KR100306123B1 (en) Core makeup tanks with pressure-balancing lines connected to a pressurizer
JP3028842B2 (en) Reactor containment vessel
CN220933769U (en) Nuclear power plant safety injection system
RU2108630C1 (en) Power unit
JPS5896288A (en) Emergency core cooling system for reactor
JPH08211181A (en) Reactor containment cooling device
JPH07159581A (en) Atomic reactor cooling facility