JPH06174871A - Light-water cooled reactor - Google Patents

Light-water cooled reactor

Info

Publication number
JPH06174871A
JPH06174871A JP4330770A JP33077092A JPH06174871A JP H06174871 A JPH06174871 A JP H06174871A JP 4330770 A JP4330770 A JP 4330770A JP 33077092 A JP33077092 A JP 33077092A JP H06174871 A JPH06174871 A JP H06174871A
Authority
JP
Japan
Prior art keywords
water
reactor
hollow portions
pool water
vessel
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.)
Withdrawn
Application number
JP4330770A
Other languages
Japanese (ja)
Inventor
Kiyoshi Kato
潔 加藤
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.)
IHI Corp
Original Assignee
IHI 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 IHI Corp filed Critical IHI Corp
Priority to JP4330770A priority Critical patent/JPH06174871A/en
Publication of JPH06174871A publication Critical patent/JPH06174871A/en
Withdrawn legal-status Critical Current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

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  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To enhance thermal efficiency and to maintain safety by isolating a reactor pressure vessel from pool water by means of a watertight container having a plurality of independent hollow portions partitioned from one another. CONSTITUTION:A watertight container surrounds and seals a reactor pressure vessel 2 and has independent, partitioned hollow portions 24a-c to accommodate heat insulating material 25. Pressurized gas supply means 26A-26C connected to the individual hollow portions supply pressurized gas to the hollow portions, the head pressure of the pressurized gas being set higher than that of pool water W. The heat insulating material 25 prevents transfer of heat from the vessel 1 to the pool water W to enhance the heat exchange efficiency of a steam generator 3. When a pressurized atmosphere is created in each of the hollow portions by operation of the means 26A-26C, water is not allowed to flow into the hollow portions because of the pressure higher than that of the pool water W, and the strength of the wall of the container 24 is increased by settings that take into account the difference in water head between the pool water W and each hollow portion, so as to prevent deformation of the heat insulating material 25 due to compression. Should water leak from through piping, etc., and enter the hollow portions 4a-c, because the hollow portions are partitioned from one another the area immersed in the water is restricted to one hollow portion to avoid thermal impact from being exerted to the whole part of the vessel 1 so as to maintain the safety of the reactor.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、軽水冷却型原子炉に係
り、特に、プール水中に原子炉圧力容器を水漬け状態に
配する技術に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a light water cooling type nuclear reactor, and more particularly to a technique for placing a reactor pressure vessel in pool water in a submerged state.

【0002】[0002]

【従来の技術】図2は、特開平3−252593号公報
(燃料集合体の交換装置)、特開平3−252594号
公報(燃料集合体の交換装置)、特開平3−25259
5号公報(燃料集合体の交換装置)に記載されている軽
水冷却型原子炉の例を示すものである。
2. Description of the Related Art FIG. 2 is a Japanese Unexamined Patent Publication No. 3-252593 (fuel assembly exchange device), Japanese Unexamined Patent Publication No. 3-252594 (fuel assembly exchange device), and Japanese Unexamined Patent Publication No. 3-25259.
5 shows an example of a light water cooled nuclear reactor described in Japanese Patent Publication No. 5 (fuel assembly exchange device).

【0003】図2において、符号1は原子炉圧力容器、
2は炉心、3は蒸気発生器、6は一次冷却水ポンプ、1
5はライザ管、16はポイズンタンク、17は冷却水入
口、18は水圧作動弁、19はポイズン流通器、20は
炉心支持板、Pはほう酸水(炉内プール水)である。
In FIG. 2, reference numeral 1 is a reactor pressure vessel,
2 is a core, 3 is a steam generator, 6 is a primary cooling water pump, 1
Reference numeral 5 is a riser pipe, 16 is a poison tank, 17 is a cooling water inlet, 18 is a water pressure operated valve, 19 is a poison distributor, 20 is a core support plate, and P is boric acid water (pool water in the reactor).

【0004】このような構造を有する原子炉にあって
は、一次冷却水及びほう酸水Pが、運転時、ポンプ停止
時の相違によって、以下に記述するように異なった流通
(循環)をする。
In the nuclear reactor having such a structure, the primary cooling water and the boric acid water P flow differently (circulate) as described below depending on the difference between the operation and the stop of the pump.

【0005】運転時にあっては、一次冷却水が、図2に
実線の矢印で示すように、炉心2、ライザ管15、一次
冷却水ポンプ6、蒸気発生器3、冷却水入口17を経由
して炉心2に戻る循環流となるが、ほう酸水Pは、水圧
作動弁18及びポイズン流通器19の部分で隔離され
て、挿通する現象や混合し合う現象の発生が妨げられ、
したがって、一次冷却水中のほう酸水濃度が変化するこ
となく、定常運転状態が維持される。
During operation, the primary cooling water passes through the core 2, the riser pipe 15, the primary cooling water pump 6, the steam generator 3, and the cooling water inlet 17, as shown by the solid arrow in FIG. However, the boric acid water P is isolated by the hydraulically operated valve 18 and the poison distributor 19 to prevent the phenomenon of insertion and the phenomenon of mixing.
Therefore, the steady operation state is maintained without changing the boric acid water concentration in the primary cooling water.

【0006】そして、一次冷却水ポンプ6の停止時にあ
っては、蒸気発生器3への送り込みが行なわれなくなる
とともに、一次冷却水ポンプ6の吐出圧力低下検出によ
って水圧作動弁18が管路を開放した状態となり、ま
た、炉心2において引き続き加熱された一次冷却水の上
昇が生じるために、図2に破線の矢印で示すように、上
昇した一次冷却水がポイズンタンク16の内部に送り出
されるとともに、ほう酸水Pがポイズン流通器19を経
由して炉心2に流れ込み、炉心2のほう酸水濃度が高ま
ることによって核分裂反応が抑制されて自然停止に導か
れる。
When the primary cooling water pump 6 is stopped, the steam generator 3 is not fed, and when the discharge pressure drop of the primary cooling water pump 6 is detected, the hydraulically operated valve 18 opens the pipeline. In addition, since the primary cooling water continuously heated in the core 2 rises, the raised primary cooling water is sent out to the inside of the poison tank 16 as shown by a dashed arrow in FIG. The boric acid water P flows into the core 2 via the poison distributor 19 and the concentration of boric acid in the core 2 increases, whereby the fission reaction is suppressed and the suspension is led to a natural stop.

【0007】[0007]

【発明が解決しようとする課題】しかし、このような構
造の原子炉にあっては、ポイズンタンク16の内外が高
温状態の一次冷却水によって囲まれた状態となってお
り、原子炉の出力が変化すると、ほう酸水Pの液量が膨
張収縮に基づいて変化し、このため、ポイズン流通器1
9の部分において一次冷却水とほう酸水Pとの境界が変
動し易く、原子炉出力の制御性が損われ易くなるという
解決すべき課題が残されている。
However, in the reactor having such a structure, the inside and outside of the poison tank 16 are surrounded by the primary cooling water at a high temperature, and the output of the reactor is When it changes, the amount of boric acid water P changes due to expansion and contraction.
In the section 9 there is still a problem to be solved that the boundary between the primary cooling water and the boric acid water P is likely to fluctuate and the controllability of the reactor power is likely to be impaired.

【0008】本発明は、上記課題を有効に解決するもの
で、原子炉の遮蔽性と制御性とを高めるとともに、熱効
率の向上と安全性の確保とを図るものである。
The present invention effectively solves the above problems, and aims to improve the shielding and controllability of a nuclear reactor, improve the thermal efficiency, and ensure the safety.

【0009】[0009]

【課題を解決するための手段】原子炉格納容器のプール
水中に原子炉圧力容器が水漬状態に配される軽水冷却型
原子炉において、原子炉圧力容器の回りに配され上下に
区画独立した複数の中空部を有する水密容器と、各中空
部に収納される断熱材と、各中空部に接続され内部を加
圧雰囲気とする加圧気体供給手段とを具備する構成を採
用している。
[Means for Solving the Problems] In a light water cooling type reactor in which the reactor pressure vessel is submerged in the pool water of the reactor containment vessel, it is arranged around the reactor pressure vessel and divided into upper and lower sections. A configuration is provided that includes a watertight container having a plurality of hollow portions, a heat insulating material housed in each hollow portion, and a pressurized gas supply unit connected to each hollow portion and having a pressurized atmosphere inside.

【0010】[0010]

【作用】原子炉圧力容器の回りにプール水が介在するこ
とにより、原子炉格納容器外への放射線漏洩が低減する
とともに、原子炉圧力容器からプール水への熱伝達は断
熱材によって妨げられる。水密容器の中空部が加圧雰囲
気とされることによって、原子炉圧力容器との圧力差の
減少とプール水等の侵入の抑制とが図られ、中空部に一
次冷却水やプール水が侵入した場合には、水浸範囲が区
画された一つの中空部の範囲にとどまる。
The pool water around the reactor pressure vessel reduces radiation leakage to the outside of the containment vessel, and the heat transfer from the reactor pressure vessel to the pool water is hindered by the heat insulating material. By making the hollow part of the watertight container a pressurized atmosphere, the pressure difference with the reactor pressure container was reduced and the ingress of pool water etc. was suppressed, and the primary cooling water and pool water invaded the hollow part. In some cases, the water immersion area is limited to the area of one hollow portion.

【0011】[0011]

【実施例】図1は、本発明に係る軽水冷却型原子炉の一
実施例を示すものである。図1にあって、符号18は給
液制御手段(例えば水圧作動弁)、21は原子炉格納容
器、22はポイズンタンク、23は給液系配管、23a
は均圧用配管、23bは給液用配管、24は水密容器、
24aは上方中空部、24bは中央中空部、24cは下
方中空部、25は断熱材、26Aは加圧装置(上部用加
圧装置)、26Bは加圧装置(中央部用加圧装置)、2
6Cは下部用加圧装置(加圧装置)、Wはプール水であ
る。
FIG. 1 shows an embodiment of a light water cooling type nuclear reactor according to the present invention. In FIG. 1, reference numeral 18 is a liquid supply control means (for example, a water pressure operated valve), 21 is a reactor containment vessel, 22 is a poison tank, 23 is a liquid supply system pipe, and 23a.
Is a pressure equalizing pipe, 23b is a liquid supply pipe, 24 is a watertight container,
Reference numeral 24a is an upper hollow portion, 24b is a central hollow portion, 24c is a lower hollow portion, 25 is a heat insulating material, 26A is a pressure device (upper pressure device), 26B is a pressure device (central pressure device), Two
6C is a lower pressurizing device (pressurizing device), and W is pool water.

【0012】前記原子炉格納容器21のプール水Wの中
には、原子炉圧力容器1やポイズンタンク22が水漬状
態に配される。
In the pool water W of the reactor containment vessel 21, the reactor pressure vessel 1 and the poison tank 22 are placed in a submerged state.

【0013】前記ポイズンタンク22は、原子炉格納容
器21の内壁に支持された状態で上方位置に配され、例
えば原子炉圧力容器1と同程度の耐圧性を持つように設
定されるとともに、高濃度のほう酸水Pを貯留する。
The poison tank 22 is arranged at an upper position while being supported by the inner wall of the reactor containment vessel 21, is set to have a pressure resistance comparable to that of the reactor pressure vessel 1, and has a high pressure. The boric acid water P having a concentration is stored.

【0014】前記給液系配管23は、原子炉圧力容器1
とポイズンタンク22との間にこれらを接続するように
給液制御手段18を介在させた状態で配される。そし
て、原子炉圧力容器1の上部位置とポイズンタンク22
の上部位置との間が、給液制御手段18を介在させた状
態の均圧用配管23aによって接続され、原子炉圧力容
器1の下部位置とポイズンタンク22の下部位置との間
が給液用配管23bによって接続されている。
The liquid supply system piping 23 is used for the reactor pressure vessel 1.
And the poison tank 22 are arranged with the liquid supply control means 18 interposed so as to connect them. The upper position of the reactor pressure vessel 1 and the poison tank 22
Is connected by a pressure equalizing pipe 23a with the liquid supply control means 18 interposed, and a liquid supply pipe is provided between the lower position of the reactor pressure vessel 1 and the lower position of the poison tank 22. It is connected by 23b.

【0015】前記水密容器24は、原子炉圧力容器1の
回りにこれを取り囲んで密閉するように配され、上下に
区画独立した複数の中空部(図1にあっては上方中空部
24a、中央中空部24b及び下方中空部24c)を有
している。
The watertight container 24 is arranged around the reactor pressure vessel 1 so as to surround and close the reactor pressure vessel 1 and is divided into a plurality of vertically separated hollow portions (in FIG. 1, an upper hollow portion 24a, a central portion). It has a hollow portion 24b and a lower hollow portion 24c).

【0016】前記断熱材25は、各中空部24a,24
b,24cに収納されて、原子炉圧力容器1からプール
水Wへの熱伝達を抑制するものである。
The heat insulating material 25 includes hollow portions 24a, 24
b and 24c, heat transfer from the reactor pressure vessel 1 to the pool water W is suppressed.

【0017】前記各加圧気体供給手段26A,26B,
26Cは、各中空部24a,24b,24cに個別に接
続されて、プール水Wの水頭圧よりも若干高く設定した
加圧空気等の加圧気体を、各中空部24a,24b,2
4cに供給し、各中空部24a,24b,24cを、少
なくとも、プール水Wの水頭圧よりも高い加圧雰囲気と
して、断熱材25が圧縮される変形を防止するものであ
る。
Each of the pressurized gas supply means 26A, 26B,
26C is individually connected to each of the hollow portions 24a, 24b, 24c, and a pressurized gas such as pressurized air set to be slightly higher than the head pressure of the pool water W is supplied to each of the hollow portions 24a, 24b, 2c.
4c, and the hollow portions 24a, 24b, 24c are set to a pressurized atmosphere at least higher than the head pressure of the pool water W to prevent the heat insulating material 25 from being compressed and deformed.

【0018】このような構造の軽水冷却型原子炉である
と、原子炉の運転時に一次冷却水ポンプ6が作動させら
れていると、炉心2で加熱されて高温状態となった一次
冷却水が、図1に実線の矢印で示すように、ライザ管1
5、一次冷却水ポンプ6、蒸気発生器3、冷却水入口1
7を経由して炉心2に戻る循環流となり、この際に、蒸
気発生器3の部分における熱交換によって、蒸気の発生
と一次冷却水の冷却とが行なわれる。
In the light water cooling type reactor having such a structure, when the primary cooling water pump 6 is operated during the operation of the nuclear reactor, the primary cooling water heated in the core 2 to a high temperature state is generated. , The riser tube 1 as shown by the solid arrow in FIG.
5, primary cooling water pump 6, steam generator 3, cooling water inlet 1
A circulation flow returns to the core 2 via 7 and at this time, steam is generated and primary cooling water is cooled by heat exchange in the steam generator 3.

【0019】そして、一次冷却水ポンプ6の吐出圧力が
均圧用配管23aを経由して給液制御手段18にそれぞ
れ伝送されることによって、給液制御手段18が均圧用
配管23aの管路を遮断した状態を保持し続ける。この
場合にあって、原子炉圧力容器1の下方位置とポイズン
タンク22の下方位置とが接続されているために、一次
冷却水の圧力上昇とともに、給液用配管23bの中のほ
う酸水Pが若干押し上げられた位置で平衡する。したが
って、ポイズンタンク22のほう酸水Pが原子炉圧力容
器1の内部に注入されることがなく、原子炉圧力容器1
の内部に収納されている一次冷却水及びほう酸水量に基
づいて運転がなされる。
The discharge pressure of the primary cooling water pump 6 is transmitted to the liquid supply control means 18 via the pressure equalization pipe 23a, so that the liquid supply control means 18 shuts off the pipe of the pressure equalization pipe 23a. Continue to hold the state. In this case, since the lower position of the reactor pressure vessel 1 and the lower position of the poison tank 22 are connected, the pressure of the primary cooling water rises and the boric acid water P in the liquid supply pipe 23b becomes Equilibrate at a slightly elevated position. Therefore, the boric acid water P in the poison tank 22 is not injected into the reactor pressure vessel 1, and the reactor pressure vessel 1
The operation is performed based on the amounts of primary cooling water and boric acid water stored in the inside of the.

【0020】また、原子炉圧力容器1の回りにプール水
Wが介在すると、プール水Wの部分で放射線の吸収が行
なわれて、外部への放射線漏洩量が低減するとともに、
原子炉圧力容器1の回りに、断熱材25が配されること
により、原子炉圧力容器1からプール水Wへの熱伝達が
断熱材25によって妨げられて、蒸気発生器3の熱交換
効率が上昇するものとなる。
When the pool water W intervenes around the reactor pressure vessel 1, the pool water W absorbs radiation, reducing the amount of radiation leaked to the outside.
By disposing the heat insulating material 25 around the reactor pressure vessel 1, the heat transfer from the reactor pressure vessel 1 to the pool water W is hindered by the heat insulating material 25, and the heat exchange efficiency of the steam generator 3 is improved. It will rise.

【0021】一方、各加圧気体供給手段26A,26
B,26Cが作動状態とされて、水密容器24における
各中空部24a,24b,24cが加圧雰囲気となって
いると、プール水Wよりも圧力が高くなっていることに
基づいて水が侵入することがなく、かつ、プール水Wの
水頭圧との差を考慮した設定をすることによって、水密
容器24の容器壁強度を高めることができる。
On the other hand, each pressurized gas supply means 26A, 26
When B and 26C are activated and the hollow portions 24a, 24b and 24c of the watertight container 24 are in a pressurized atmosphere, water invades based on the fact that the pressure is higher than the pool water W. Without doing so, the strength of the container wall of the watertight container 24 can be increased by setting in consideration of the difference with the head pressure of the pool water W.

【0022】水密容器24における各中空部24a,2
4b,24cに、これらの部分を貫通している配管等か
らの漏洩によって、水が入り込むような事態が生じた場
合について検討すると、各中空部24a,24b,24
cが区画されて独立していることにより、水浸範囲が区
画された一つの中空部の範囲にとどまって、原子炉圧力
容器1の外表面の全域に熱衝撃を及ぼすことが回避され
る。
Each hollow portion 24a, 2 of the watertight container 24
Examining the case where water enters the 4 b and 24 c due to leakage from pipes penetrating these parts, the hollow parts 24 a, 24 b and 24
Since c is partitioned and independent, it is possible to prevent the water immersion area from staying within the defined one hollow portion and causing a thermal shock to the entire outer surface of the reactor pressure vessel 1.

【0023】なお、原子炉の運転中に、停電や故障等の
原因に基づいて一次冷却水ポンプ6が停止した場合に
は、以下に説明するように、原子炉が受動的に自然停止
状態に導かれる。
When the primary cooling water pump 6 is stopped due to a cause such as a power failure or a failure during the operation of the reactor, the reactor is passively brought into a natural stop state as described below. Be guided.

【0024】一次冷却水ポンプ6が停止すると、ポンプ
吐出圧力の低下または圧力消滅が、均圧用配管23aを
経由して給液制御手段18に伝達され、給液制御手段1
8の作動によって均圧用配管23aによる管路が開放状
態に導かれる。
When the primary cooling water pump 6 is stopped, the decrease or disappearance of the pump discharge pressure is transmitted to the liquid supply control means 18 via the pressure equalizing pipe 23a, and the liquid supply control means 1 is supplied.
By the operation of 8, the pipe line by the pressure equalizing pipe 23a is guided to the open state.

【0025】原子炉圧力容器1の下部位置とポイズンタ
ンク22の下部位置との連通に加えて、原子炉圧力容器
1の上部位置とポイズンタンク22の上部位置とが接続
されることによって、原子炉圧力容器1の気相部分の蒸
気がポイズンタンク22に送り込まれて、ポイズンタン
ク22に気相部分が形成されることによる均圧化が図ら
れ、ポイズンタンク22と原子炉圧力容器1との水頭差
に基づいて、ほう酸水Pが図1の破線の矢印で示すよう
に、原子炉圧力容器1の内部に注入される。ほう酸水P
が炉心2に送り込まれると、炉心2の冷却と核反応抑制
とによって原子炉が自然停止状態に導かれる。
In addition to the communication between the lower position of the reactor pressure vessel 1 and the lower position of the poison tank 22, the upper position of the reactor pressure vessel 1 and the upper position of the poison tank 22 are connected to each other. The vapor in the vapor phase portion of the pressure vessel 1 is sent to the poison tank 22 to form the vapor phase portion in the poison tank 22 so that the pressure is equalized, and the head of the poison tank 22 and the reactor pressure vessel 1 is headed. Based on the difference, the boric acid water P is injected into the reactor pressure vessel 1 as shown by the dashed arrow in FIG. Boric acid water P
Is sent to the core 2, the reactor is brought into a spontaneous shutdown state by cooling the core 2 and suppressing the nuclear reaction.

【0026】原子炉運転中に、一次冷却系のなんらかの
故障に起因して、炉水が低下する現象が発生した場合
(冷却材喪失時)には、一次冷却水の水位レベルが一次
冷却水ポンプ6のポンプ吸引口の下方位置まで低下する
と、一次冷却水ポンプ6が気体分を吸い込むことに基づ
いて吐出圧力が低下し、一次冷却水ポンプ6が停止した
場合と同様に、給液制御手段18が均圧用配管23aの
管路を開放し、ポイズンタンク22のほう酸水Pが炉心
2に送り込まれ、炉心2の冠水状態の保持と原子炉停止
とが行なわれる。
During the operation of the reactor, when a phenomenon occurs in which the reactor water drops due to some failure of the primary cooling system (when the coolant is lost), the level of the primary cooling water is changed to the primary cooling water pump. When it is lowered to a position below the pump suction port of 6, the discharge pressure is lowered due to the primary cooling water pump 6 sucking in the gas component, and the liquid supply control means 18 is provided as in the case where the primary cooling water pump 6 is stopped. Opens the line of the pressure equalizing pipe 23a, the boric acid water P in the poison tank 22 is sent to the core 2, and the submerged state of the core 2 is maintained and the reactor is stopped.

【0027】[0027]

【発明の効果】本発明に係る軽水冷却型原子炉によれ
ば、原子炉格納容器のプール水中に原子炉圧力容器が水
漬状態に配されることに基づく原子炉の遮蔽性や、ポイ
ズンタンクを原子炉格納容器の内部に設置することに基
づく原子炉出力の制御性の改善等に加えて、以下の効果
を奏する。 (1) 原子炉圧力容器の回りが、独立した複数の中空
部を有する水密容器によって囲まれてプール水から隔離
されるので、原子炉圧力容器からプール水への熱伝達を
抑制して原子炉の熱効率の向上を図ることができる。 (2) 各中空部が加圧雰囲気に保持されることによ
り、断熱材の形状を保持して断熱性を確保することに加
えて、プール水との圧力差を低減して水密容器の強度を
向上させることができる。 (3) 水密容器の内部に水が侵入した場合にあって
は、水浸範囲を複数の中空部の一つにとどめて、熱衝撃
が原子炉圧力容器の全体に及ぶことを回避して、原子炉
の安全性を確保することができる。
EFFECTS OF THE INVENTION According to the light water cooling type reactor of the present invention, the shielding property of the reactor based on the fact that the reactor pressure vessel is submerged in the pool water of the reactor containment vessel, and the poison tank. In addition to improving the controllability of the reactor power based on the installation of the inside of the reactor containment vessel, the following effects are exhibited. (1) Since the area around the reactor pressure vessel is surrounded by the watertight vessel having a plurality of independent hollow portions and is isolated from the pool water, the heat transfer from the reactor pressure vessel to the pool water is suppressed and the reactor is suppressed. The thermal efficiency of can be improved. (2) By holding each hollow part in a pressurized atmosphere, the shape of the heat insulating material is maintained to ensure heat insulation, and the pressure difference with the pool water is reduced to increase the strength of the watertight container. Can be improved. (3) When water enters the watertight container, the water immersion area is limited to one of the hollow parts to prevent thermal shock from reaching the entire reactor pressure container, The safety of the nuclear reactor can be secured.

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

【図1】本発明に係る軽水冷却型原子炉の一実施例を示
す正断面図である。
FIG. 1 is a front sectional view showing an embodiment of a light water cooling-type nuclear reactor according to the present invention.

【図2】軽水冷却型原子炉の従来例を示す正断面図であ
る。
FIG. 2 is a front sectional view showing a conventional example of a light water cooling type nuclear reactor.

【符号の説明】[Explanation of symbols]

1 原子炉圧力容器 2 炉心 3 蒸気発生器 6 一次冷却水ポンプ 15 ライザ管 17 冷却水入口 18 給液制御手段(水圧作動弁) 21 原子炉格納容器 22 ポイズンタンク 23 給液系配管 23a 均圧用配管 23b 給液用配管 24 水密容器 24a 上方中空部 24b 中央中空部 24c 下方中空部 25 断熱材 26A 加圧気体供給手段(上部用加圧装置) 26B 加圧気体供給手段(中央部用加圧装置) 26C 加圧気体供給手段(下部用加圧装置) P ほう酸水(炉内プール水) W プール水 1 Reactor Pressure Vessel 2 Core 3 Steam Generator 6 Primary Cooling Water Pump 15 Riser Pipe 17 Cooling Water Inlet 18 Liquid Supply Control Means (Water Pressure Operated Valve) 21 Reactor Containment Vessel 22 Poison Tank 23 Liquid Supply System Pipe 23a Pressure Equalizing Pipe 23b Liquid supply pipe 24 Watertight container 24a Upper hollow part 24b Central hollow part 24c Lower hollow part 25 Heat insulating material 26A Pressurized gas supply means (upper pressurizing device) 26B Pressurized gas supply means (central part pressurizing device) 26C Pressurized gas supply means (pressurizing device for lower part) P Boric acid water (pool water in furnace) W pool water

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 原子炉格納容器のプール水中に原子炉圧
力容器が水漬状態に配される軽水冷却型原子炉であっ
て、原子炉圧力容器の回りに配され上下に区画独立した
複数の中空部を有する水密容器と、各中空部に収納され
る断熱材と、各中空部に接続され内部を加圧雰囲気とす
る加圧気体供給手段とを具備することを特徴とする軽水
冷却型原子炉。
1. A light water cooling type reactor in which the reactor pressure vessel is placed in the pool water of the reactor containment vessel in a submerged state. A light water-cooled atom comprising: a watertight container having a hollow portion; a heat insulating material housed in each hollow portion; and a pressurized gas supply means connected to each hollow portion and having a pressurized atmosphere inside thereof. Furnace.
JP4330770A 1992-12-10 1992-12-10 Light-water cooled reactor Withdrawn JPH06174871A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP4330770A JPH06174871A (en) 1992-12-10 1992-12-10 Light-water cooled reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP4330770A JPH06174871A (en) 1992-12-10 1992-12-10 Light-water cooled reactor

Publications (1)

Publication Number Publication Date
JPH06174871A true JPH06174871A (en) 1994-06-24

Family

ID=18236351

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4330770A Withdrawn JPH06174871A (en) 1992-12-10 1992-12-10 Light-water cooled reactor

Country Status (1)

Country Link
JP (1) JPH06174871A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103440886A (en) * 2013-08-20 2013-12-11 上海核工程研究设计院 Device for increasing critical heat flux density of outer wall surface of pressure vessel
KR101456575B1 (en) * 2013-03-05 2014-10-31 한국원자력연구원 In vessel boron injection system
US10699816B2 (en) 2015-03-19 2020-06-30 Hydromine Nuclear Energy S.A.R.L. Nuclear reactor, in particular liquid-metal-cooled compact nuclear reactor

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101456575B1 (en) * 2013-03-05 2014-10-31 한국원자력연구원 In vessel boron injection system
CN103440886A (en) * 2013-08-20 2013-12-11 上海核工程研究设计院 Device for increasing critical heat flux density of outer wall surface of pressure vessel
US10699816B2 (en) 2015-03-19 2020-06-30 Hydromine Nuclear Energy S.A.R.L. Nuclear reactor, in particular liquid-metal-cooled compact nuclear reactor

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