JPH06265677A - Light water cooled reactor - Google Patents

Light water cooled reactor

Info

Publication number
JPH06265677A
JPH06265677A JP5049643A JP4964393A JPH06265677A JP H06265677 A JPH06265677 A JP H06265677A JP 5049643 A JP5049643 A JP 5049643A JP 4964393 A JP4964393 A JP 4964393A JP H06265677 A JPH06265677 A JP H06265677A
Authority
JP
Japan
Prior art keywords
reactor
pressure vessel
wall
water
isolation wall
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Withdrawn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
JP5049643A
Other languages
Japanese (ja)
Inventor
Kiyoshi Kato
潔 加藤
Tatsuya Shioda
達也 塩田
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 JP5049643A priority Critical patent/JPH06265677A/en
Publication of JPH06265677A publication Critical patent/JPH06265677A/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Withdrawn legal-status Critical Current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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To make the execution of regular inspection at welding parts and the like easy by arranging an isolation wall between the lower part of a reactor container and the lower part of a reactor pressure vessel for storing pool water at the upper part and forming drywell at the lower part. CONSTITUTION:An isolation wall 31 is arranged between the lower part of a reactor container 21 and a water seal tank 24 or between the lower part of the containment 21 and the lower part of a reactor pressure vessel 1 so as to separate an annular space up and down. At the boundary of spherical wall 21a and cylindrical wall 21b of the containment 21, the wall is formed annularly in the way a part of the spherical wall 21a is extended inside. Above the isolation wall 31, pool water W is stored and a drywell 32 is formed below. By constituting this way, in executing maintenance of the pressure vessel 1 in a regular inspection and the like, by opening an opening cover in the component introduction hatch 33, a worker can easily go inside a containment 21.

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4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. 4 shows Japanese Unexamined Patent Publication No. Hei 3-252593 (fuel assembly exchange device), Japanese Unexamined Patent Publication No. 3-252594 (fuel assembly exchange device), Japanese Unexamined Patent Publication No. Hei 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4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. 4, 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4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4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】このような図4例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19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。
In the reactor shown in FIG. 4, the inside and outside of the poison tank 16 are surrounded by the primary cooling water at a high temperature, and when the output of the reactor changes, the boric acid water P The amount of liquid changes due to expansion and contraction, and therefore, the boundary between the primary cooling water and the boric acid water P easily changes in the portion of the poison distributor 19 and the controllability of the reactor output is likely to be impaired.

【0008】次いで、図5例は、軽水冷却型原子炉の他
の構造例(計画例)を示すものである。該計画例にあっ
ては、原子炉格納容器21のプール水Wの中に、原子炉
圧力容器1が水漬状態に配され、ポイズンタンク22も
プール水Wの中に配される。そして、原子炉圧力容器1
とポイズンタンク22との間が、給液系配管23を構成
する均圧用配管23a及び給液用配管23bによって接
続される。この構造とすることによって、ポイズンタン
ク22が低温状態のプール水Wに収容されて、原子炉圧
力容器1からの熱的な隔離と、一次冷却水とほう酸水P
との隔離とを行なうとともに、落差及び比重差を利用し
たほう酸水Pの供給により原子炉を自然停止状態に導く
ことが可能となり、加えて、ほう酸水Pの容量を大容量
とすることができる。
Next, FIG. 5 shows another structural example (plan example) of the light water cooling type reactor. In the plan example, the reactor pressure vessel 1 is placed in the pool water W of the reactor containment vessel 21 in a state of being immersed in water, and the poison tank 22 is also placed in the pool water W. And the reactor pressure vessel 1
And the poison tank 22 are connected by a pressure equalizing pipe 23a and a liquid supply pipe 23b which constitute the liquid supply system pipe 23. With this structure, the poison tank 22 is housed in the pool water W in a low temperature state, and is thermally isolated from the reactor pressure vessel 1, and the primary cooling water and the boric acid water P are contained.
It is possible to bring the reactor into a natural shutdown state by supplying the boric acid water P using the drop and the specific gravity difference, and to increase the capacity of the boric acid water P to a large capacity. .

【0009】[0009]

【発明が解決しようとする課題】しかしながら、図5例
の原子炉にあっては、原子炉圧力容器1の回りにプール
水Wが介在しているために、特に、放射線照射量の多く
なる部分、つまり、炉心2の近傍に位置している原子炉
圧力容器1の下部側壁等の定期検査を実施しようとした
場合に、全部のプール水Wを排出してその付近を大気雰
囲気とするか、あるいは水中での検査が必要であり、そ
の労力が多大なものとなる。そして、原子炉圧力容器1
の回りには、水密タンク24及びその内部に断熱材25
が配されて、原子炉圧力容器1の内部の原子炉冷却水と
プール水Wとの熱交換を抑制するようにしているが、こ
れら水密タンク24及び断熱材25の存在も、定期検査
実施の際における作業性低下の一因となる。
However, in the reactor shown in FIG. 5, the pool water W intervenes around the reactor pressure vessel 1, so that the radiation dose is particularly large in the portion. That is, when attempting to carry out a periodical inspection of the lower side wall and the like of the reactor pressure vessel 1 located near the core 2, all pool water W is discharged to create an atmosphere in the vicinity thereof, Alternatively, an inspection underwater is necessary, which requires a great deal of labor. And the reactor pressure vessel 1
The watertight tank 24 and heat insulating material 25
Are arranged to suppress heat exchange between the reactor cooling water inside the reactor pressure vessel 1 and the pool water W. However, the presence of the watertight tank 24 and the heat insulating material 25 also causes a periodic inspection. This is one of the causes of a decrease in workability.

【0010】本発明は、上記課題を有効に解決するもの
で、原子炉圧力容器における溶接部等の定期検査の実
施を容易にすること、炉心の近傍における原子炉圧力
容器と原子炉格納容器との熱遮断構造を簡素化するこ
と、原子炉冷却水とプール水との熱交換を妨げること
を目的としている。
The present invention effectively solves the above problems and facilitates the periodic inspection of welded parts in a reactor pressure vessel, and the reactor pressure vessel and the reactor containment vessel in the vicinity of the core. The objective is to simplify the heat-shielding structure and prevent heat exchange between the reactor cooling water and pool water.

【0011】[0011]

【課題を解決するための手段】かかる課題を解決するた
めの複数の手段を提案する。第1の手段は、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、原子炉格納容器の下部と
原子炉圧力容器の下部との間に、上方にプール水を貯留
させかつ下方にドライウエルを形成する隔離壁が配設さ
れる構成を採用している。第2の手段は、第1の手段
に、隔離壁が、原子炉圧力容器の回りの断熱材を囲む水
密容器と原子炉格納容器の下部との間に配される構成を
付加している。第3の手段は、第1の手段に、原子炉格
納容器の下部に、水密容器を貫通しかつ隔離壁よりも下
方に位置する機器搬入ハッチが配される構成を付加して
いる。第4の手段は、第2の手段または第3の手段に、
ドライウエルにおける水密容器の内面に機器搬送路が配
される構成を付加している。
[Means for Solving the Problems] Several means for solving the problems are proposed. A first means is a light water cooling type reactor in which the reactor pressure vessel is immersed in pool water of the reactor containment vessel between a lower part of the reactor containment vessel and a lower part of the reactor pressure vessel. , A structure in which an isolation wall that stores pool water above and forms a dry well below is disposed. The second means adds to the first means a structure in which the isolation wall is arranged between the watertight container surrounding the heat insulating material around the reactor pressure vessel and the lower portion of the reactor containment vessel. In the third means, in addition to the first means, an equipment carry-in hatch which penetrates the watertight container and is located below the isolation wall is arranged below the reactor containment vessel. The fourth means is the second means or the third means,
A configuration in which a device transport path is arranged on the inner surface of the watertight container in the dry well is added.

【0012】[0012]

【作用】第1の手段にあっては、隔離壁よりも上方にプ
ール水が貯留されて、原子炉圧力容器が水漬状態となる
が、隔離壁よりも下方では原子炉圧力容器の回りがドラ
イウエルとされて、炉心近傍の原子炉圧力容器の回りの
メンテナンス性が向上する。第2の手段にあっては、第
1の手段による作用に加えて、原子炉格納容器の下部と
原子炉圧力容器の下部との間が、水密容器によって区画
されるとともに、水密容器の回りがドライウエルとさ
れ、この近傍における原子炉冷却水とプール水との熱交
換量が低減する。第3の手段にあっては、第1の手段に
よる作用に加えて、原子炉格納容器の下部において、外
部と水密容器の内部とが、機器搬入ハッチを介して接続
され、外部から原子炉圧力容器表面近傍への検査機器類
の搬入が行なわれる。第4の手段にあっては、第2の手
段または第3の手段による作用に加えて、水密容器の内
面に配される機器搬送路によって、原子炉圧力容器の表
面に沿った検査機器類の移動が実施され、原子炉のメン
テナンス性が向上する。
In the first means, pool water is stored above the isolation wall, and the reactor pressure vessel is kept in a water immersion state, but below the isolation wall, the area around the reactor pressure vessel is As a dry well, the maintainability around the reactor pressure vessel near the core is improved. In the second means, in addition to the function of the first means, the lower part of the reactor containment vessel and the lower part of the reactor pressure vessel are partitioned by a watertight container, and the area around the watertight container is This is a dry well, and the amount of heat exchange between the reactor cooling water and the pool water in this vicinity is reduced. In the third means, in addition to the function of the first means, the outside of the reactor containment vessel and the inside of the watertight vessel are connected to each other via the equipment carry-in hatch, and the reactor pressure is applied from the outside. Inspection equipment is brought in near the surface of the container. In the fourth means, in addition to the action of the second means or the third means, the equipment transport path arranged on the inner surface of the watertight container allows the inspection equipment along the surface of the reactor pressure vessel to be installed. The move will be implemented and the maintainability of the reactor will be improved.

【0013】[0013]

【実施例】以下、本発明に係る軽水冷却型原子炉の一実
施例について、図1ないし図3に基づいて説明する。該
一実施例においても、原子炉格納容器21のプール水W
の中に、原子炉圧力容器1が水漬状態に配される軽水冷
却型原子炉に適用され、各図において、符号31は隔離
壁、32はドライウエル、33は機器搬入ハッチ、34
は機器搬送路である。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of a light water cooling type nuclear reactor according to the present invention will be described below with reference to FIGS. Also in this embodiment, the pool water W in the reactor containment vessel 21
Is applied to a light water cooling type reactor in which the reactor pressure vessel 1 is placed in a submerged state. In each drawing, reference numeral 31 is an isolation wall, 32 is a dry well, 33 is an equipment carry-in hatch, 34
Is the equipment transport path.

【0014】前記隔離壁31は、図1に示すように、原
子炉格納容器21の下部と水密タンク24との間、また
は原子炉格納容器21の下部と原子炉圧力容器1の下部
との間に、環状空間を上下に区画するように配設され
る。そして、図1例にあっては、原子炉格納容器21に
おける球状壁21aと円筒状壁21bとの境界に、球状
壁21aの一部を内方に延長した状態で環状に形成され
る。
As shown in FIG. 1, the isolation wall 31 is provided between the lower part of the reactor containment vessel 21 and the watertight tank 24, or between the lower part of the reactor containment vessel 21 and the lower part of the reactor pressure vessel 1. And is arranged so as to divide the annular space into upper and lower parts. In the example of FIG. 1, the boundary between the spherical wall 21a and the cylindrical wall 21b in the reactor containment vessel 21 is formed annularly with a part of the spherical wall 21a extended inward.

【0015】隔離壁31の上方にはプール水Wが貯留さ
れるとともに、下方にはドライウエル32が形成され
る。該ドライウエル32は、図1例にあっては、原子炉
格納容器21の円筒状壁21bと水密タンク24との間
に環状空間を形成するように配され、図5例のプール水
Wに代えて空気雰囲気とされる。
Pool water W is stored above the isolation wall 31, and a dry well 32 is formed below it. In the example of FIG. 1, the dry well 32 is arranged so as to form an annular space between the cylindrical wall 21b of the reactor containment vessel 21 and the watertight tank 24. Instead, an air atmosphere is used.

【0016】前記機器搬入ハッチ33は、図2に示すよ
うに、原子炉格納容器21における円筒状壁21b、ド
ライウエル32、水密タンク24及び断熱材25をそれ
ぞれ貫通した状態に、かつ、隔離壁31よりも下方に位
置するように配される。該機器搬入ハッチ33には、円
筒状壁21bに取り付けられる水平スリーブ33aと、
該水平スリーブ33aの内方位置に円筒状壁21bと水
密タンク24との間を接続するように配されるベローズ
33bと、これら水平スリーブ33a及びベローズ33
bによって形成される搬入穴33cと、水平スリーブ3
3aの外方開口を開閉可能とするための開閉カバー33
dと、水平スリーブ33a及びベローズ33bの内底面
近傍に配される足場33eとが設けられる。
As shown in FIG. 2, the equipment carry-in hatch 33 penetrates the cylindrical wall 21b, the dry well 32, the watertight tank 24, and the heat insulating material 25 of the reactor containment vessel 21 and the isolation wall. It is arranged so as to be located below 31. The equipment carry-in hatch 33 includes a horizontal sleeve 33a attached to the cylindrical wall 21b,
Bellows 33b arranged to connect between the cylindrical wall 21b and the watertight tank 24 at an inner position of the horizontal sleeve 33a, and the horizontal sleeve 33a and the bellows 33.
carry-in hole 33c formed by b and the horizontal sleeve 3
Opening / closing cover 33 for opening / closing the outer opening of 3a
d, and a scaffold 33e arranged near the inner bottom surfaces of the horizontal sleeve 33a and the bellows 33b.

【0017】前記機器搬送路34は、ドライウエル32
の範囲内において、図2及び図3に示すように、水密タ
ンク24の内面に断熱材25から突出するように、上下
方向及び水平方向あるいは所望方向に一体に配される。
The equipment transport path 34 is provided with a dry well 32.
2 and FIG. 3, within the range, the watertight tank 24 is integrally arranged in the vertical and horizontal directions or in a desired direction so as to project from the heat insulating material 25.

【0018】このような構造の軽水冷却型原子炉である
と、プール水Wが隔離壁31で隔離されて、隔離壁31
よりも下方の部分において、原子炉格納容器21におけ
る円筒状壁21bと水密タンク24との間にドライウエ
ル32が形成されるため、ドライウエル32の内部への
作業員の立ち入りが可能になる。つまり、炉心2の近傍
位置にあっては、水密タンク24の回りがドライウエル
32とされて、水密タンク24の外表面が露出した状態
となっており、原子炉圧力容器1及び炉心2の近傍にお
ける水密タンク24あるいは円筒状壁21bのメンテナ
ンス性が向上する。
In the light water cooling type reactor having such a structure, the pool water W is isolated by the isolation wall 31, and the isolation wall 31
Since the dry well 32 is formed between the watertight tank 24 and the cylindrical wall 21b of the reactor containment vessel 21 in a portion below the dry containment vessel 21, a worker can enter the dry well 32. That is, in the vicinity of the core 2, the dry well 32 is formed around the watertight tank 24 so that the outer surface of the watertight tank 24 is exposed, and the vicinity of the reactor pressure vessel 1 and the core 2 is exposed. The maintainability of the watertight tank 24 or the cylindrical wall 21b is improved.

【0019】そして、ドライウエル32が形成されてい
ると、その部分にプール水Wが入り込んでいる場合と比
較して断熱性が向上し、原子炉圧力容器1からの放熱量
を少なくして、原子炉の熱利用が有効に行なわれるもの
となり、この範囲の断熱材25の簡素化等が達成可能に
なる。
When the dry well 32 is formed, the heat insulating property is improved as compared with the case where the pool water W enters into that portion, and the amount of heat released from the reactor pressure vessel 1 is reduced, The heat of the nuclear reactor is effectively used, and the heat insulating material 25 in this range can be simplified.

【0020】定期検査時等において、原子炉圧力容器1
のメンテナンスを実施する場合には、機器搬入ハッチ3
3における開閉カバー33dを明けることにより、原子
炉格納容器21の内部に作業員が立ち入り可能になる。
足場33eを利用して検査機器等を水密タンク24の内
部に搬入し、これら検査機器等を機器搬送路34によっ
て支持させて、原子炉圧力容器1の各所まで移動させる
等によって、所望のメンテナンスが実施されることにな
る。
At the time of periodic inspection, etc., the reactor pressure vessel 1
When carrying out maintenance of the
By opening the opening / closing cover 33d in 3, the worker can enter the inside of the reactor containment vessel 21.
By using the scaffold 33e to carry in the inspection equipment and the like into the watertight tank 24, support the inspection equipment and the like by the equipment conveyance path 34, and move them to various places in the reactor pressure vessel 1, desired maintenance can be performed. Will be implemented.

【0021】〔他の実施態様〕本発明に係る軽水冷却型
原子炉にあっては、一実施例に代えて次の技術を採用す
ることができる。 a)機器搬入ハッチ33の設置と併用して、ドライウエ
ル32の中に作業員が立ち入るためのマンホールやハッ
チ等が配されること。 b)隔離壁31が水密タンク24を貫通していない構造
である場合に、機器搬送路34が隔離壁31の上方位置
まで延長されること。 c)機器搬送路34が機器搬入ハッチ33における足場
33eまで敷設され、かつ接続されること。
[Other Embodiments] In the light water cooling type reactor according to the present invention, the following technique can be adopted instead of one embodiment. a) Manholes, hatches, etc. for workers to enter in the dry well 32 should be provided in combination with the installation of the equipment carry-in hatch 33. b) When the isolation wall 31 has a structure that does not penetrate the watertight tank 24, the equipment transport path 34 should be extended to a position above the isolation wall 31. c) The equipment transport path 34 is laid and connected to the scaffold 33e in the equipment carry-in hatch 33.

【0022】[0022]

【発明の効果】本発明に係る軽水冷却型原子炉によれ
ば、以下の効果を奏する。 (1) 原子炉格納容器の下部と原子炉圧力容器の下部
との間に、隔離壁を配してその下方にドライウエルを形
成することにより、原子炉格納容器の内部への作業員の
立ち入りや機器類の搬入が可能となり、原子炉のメンテ
ナンス性を向上させることができる。 (2) 隔離壁が、水密容器と原子炉格納容器の下部と
の間に配されることにより、水密容器の気密性を利用し
てドライウエルの形成を容易にし、この部分における原
子炉冷却水とプール水との熱交換を妨げて、原子炉の熱
効率の向上を図り、かつ、断熱構造の簡素化を図ること
ができる。 (3) 原子炉格納容器の下部に水密容器を貫通した状
態の機器搬入ハッチが配されることにより、原子炉圧力
容器の回りへの検査機器等の搬入を容易にし、定期検査
等の作業性を向上させることができる。 (4) 水密容器の内面に機器搬送路が配されることに
より、原子炉圧力容器の表面に沿った検査機器類の移動
を容易にして、原子炉のメンテナンスを効率良く実施す
ることができる。
The light water cooled nuclear reactor according to the present invention has the following effects. (1) An isolation wall is provided between the lower part of the reactor containment vessel and the lower part of the reactor pressure vessel, and a dry well is formed below the isolation wall to allow workers to enter the reactor containment vessel. And equipment can be carried in, and the maintainability of the reactor can be improved. (2) The isolation wall is arranged between the watertight container and the lower part of the reactor containment vessel to facilitate the formation of dry wells by utilizing the airtightness of the watertight container and to cool the reactor cooling water in this part. It is possible to improve the thermal efficiency of the nuclear reactor and to simplify the heat insulating structure by hindering the heat exchange between the water and the pool water. (3) By arranging the equipment carry-in hatch under the watertight container in the lower part of the reactor containment vessel, it becomes easy to carry in the inspection equipment around the reactor pressure vessel, and the workability of periodic inspection etc. Can be improved. (4) By arranging the equipment transport path on the inner surface of the watertight container, the inspection equipments can be easily moved along the surface of the reactor pressure vessel, and the reactor can be efficiently maintained.

【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】図1に示す機器搬入ハッチ部分の拡大図であ
る。
FIG. 2 is an enlarged view of a device carrying-in hatch portion shown in FIG.

【図3】図1例における機器搬送路部分の斜視図であ
る。
FIG. 3 is a perspective view of a device transport path portion in the example of FIG.

【図4】軽水冷却型原子炉の従来例を示す正断面図であ
る。
FIG. 4 is a front sectional view showing a conventional example of a light water cooling reactor.

【図5】軽水冷却型原子炉の計画例を示す正断面図であ
る。
FIG. 5 is a front cross-sectional view showing a plan example of a light water cooling 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 21 原子炉格納容器 21a 球状壁 21b 円筒状壁 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 水密タンク 25 断熱材 31 隔離壁 32 ドライウエル 33 機器搬入ハッチ 33a 水平スリーブ 33b ベローズ 33c 搬入穴 33d 開閉カバー 33e 足場 34 機器搬送路 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 21 Reactor containment vessel 21a Spherical wall 21b Cylindrical wall 22 Poison tank 23 Liquid supply piping 23a Pressure equalizing piping 23b Liquid supply piping 24 Watertight tank 25 Insulation Material 31 Isolation wall 32 Drywell 33 Equipment carry-in hatch 33a Horizontal sleeve 33b Bellows 33c Carry-in hole 33d Open / close cover 33e Scaffold 34 Equipment transport path P Boric water (pool water in reactor) W Pool water

───────────────────────────────────────────────────── フロントページの続き (51)Int.Cl.5 識別記号 庁内整理番号 FI 技術表示箇所 8908−2G G21C 13/02 GDL Q ─────────────────────────────────────────────────── ─── Continuation of the front page (51) Int.Cl. 5 Identification number Office reference number FI technical display location 8908-2G G21C 13/02 GDL Q

Claims (4)

【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、原子炉格納容器の下部と原子炉圧力容器の下部との
間に、上方にプール水を貯留させかつ下方にドライウエ
ルを形成する隔離壁が配設されることを特徴とする軽水
冷却型原子炉。
1. A light water cooled reactor in which the reactor pressure vessel is submerged in the pool water of the reactor containment vessel, and between the lower part of the reactor containment vessel and the lower part of the reactor pressure vessel. A light water cooled nuclear reactor, characterized in that an isolation wall for storing pool water in the upper part and forming a dry well is arranged in the lower part.
【請求項2】 隔離壁が、原子炉圧力容器の回りの断熱
材を囲む水密容器と原子炉格納容器の下部との間に配さ
れることを特徴とする請求項1記載の軽水冷却型原子
炉。
2. The light water cooled atom according to claim 1, wherein the isolation wall is arranged between a watertight container surrounding a heat insulating material around the reactor pressure vessel and a lower portion of the reactor containment vessel. Furnace.
【請求項3】 原子炉格納容器の下部に、水密容器を貫
通しかつ隔離壁よりも下方に位置する機器搬入ハッチが
配されることを特徴とする請求項1または2記載の軽水
冷却型原子炉。
3. The light water cooling type atom according to claim 1, wherein an equipment carry-in hatch penetrating the watertight container and located below the isolation wall is arranged in a lower portion of the reactor containment vessel. Furnace.
【請求項4】 ドライウエルにおける水密容器の内面に
機器搬送路が配されることを特徴とする請求項2または
3記載の軽水冷却型原子炉。
4. The light water cooling type nuclear reactor according to claim 2 or 3, wherein an equipment transport path is arranged on the inner surface of the watertight container in the dry well.
JP5049643A 1993-03-10 1993-03-10 Light water cooled reactor Withdrawn JPH06265677A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP5049643A JPH06265677A (en) 1993-03-10 1993-03-10 Light water cooled reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP5049643A JPH06265677A (en) 1993-03-10 1993-03-10 Light water cooled reactor

Publications (1)

Publication Number Publication Date
JPH06265677A true JPH06265677A (en) 1994-09-22

Family

ID=12836898

Family Applications (1)

Application Number Title Priority Date Filing Date
JP5049643A Withdrawn JPH06265677A (en) 1993-03-10 1993-03-10 Light water cooled reactor

Country Status (1)

Country Link
JP (1) JPH06265677A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1998031020A1 (en) * 1997-01-10 1998-07-16 Combustion Engineering, Inc. Nuclear power plant support building for cylindrical or spherical containment structures
JP2014157054A (en) * 2013-02-15 2014-08-28 Hitachi-Ge Nuclear Energy Ltd Reactor container
KR20160101938A (en) * 2013-12-26 2016-08-26 뉴스케일 파워, 엘엘씨 Neutron detection system for nuclear reactors
CN110107688A (en) * 2019-05-17 2019-08-09 江苏久维压力容器制造有限公司 Cover compression type pressure vessel

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1998031020A1 (en) * 1997-01-10 1998-07-16 Combustion Engineering, Inc. Nuclear power plant support building for cylindrical or spherical containment structures
JP2014157054A (en) * 2013-02-15 2014-08-28 Hitachi-Ge Nuclear Energy Ltd Reactor container
KR20160101938A (en) * 2013-12-26 2016-08-26 뉴스케일 파워, 엘엘씨 Neutron detection system for nuclear reactors
JP2017500580A (en) * 2013-12-26 2017-01-05 ニュースケール パワー エルエルシー Improvement of neutron path
US10466367B1 (en) 2013-12-26 2019-11-05 Nuscale Power, Llc Neutron path enhancement
CN110107688A (en) * 2019-05-17 2019-08-09 江苏久维压力容器制造有限公司 Cover compression type pressure vessel

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