Deprecated: The each() function is deprecated. This message will be suppressed on further calls in /home/zhenxiangba/zhenxiangba.com/public_html/phproxy-improved-master/index.php on line 456
JPS5939720B2 - Residual heat removal equipment - Google Patents
[go: Go Back, main page]

JPS5939720B2 - Residual heat removal equipment - Google Patents

Residual heat removal equipment

Info

Publication number
JPS5939720B2
JPS5939720B2 JP55177489A JP17748980A JPS5939720B2 JP S5939720 B2 JPS5939720 B2 JP S5939720B2 JP 55177489 A JP55177489 A JP 55177489A JP 17748980 A JP17748980 A JP 17748980A JP S5939720 B2 JPS5939720 B2 JP S5939720B2
Authority
JP
Japan
Prior art keywords
water
reactor
pipe
pool
residual heat
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.)
Expired
Application number
JP55177489A
Other languages
Japanese (ja)
Other versions
JPS57100388A (en
Inventor
克治 前田
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP55177489A priority Critical patent/JPS5939720B2/en
Publication of JPS57100388A publication Critical patent/JPS57100388A/en
Publication of JPS5939720B2 publication Critical patent/JPS5939720B2/en
Expired 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
    • 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)

Description

【発明の詳細な説明】 本発明は沸騰水形原子炉の残留熱除去装置に関する。[Detailed description of the invention] The present invention relates to a residual heat removal device for a boiling water nuclear reactor.

一般に沸騰水形原子炉には残留熱除去装置が設けられて
おり、原子炉停止時等において原子炉圧力容器内の炉水
を取出して熱交換器を介して循環させ、炉心で発生する
崩壊熱等の残留熱を除去するように構成されている。
Generally, boiling water reactors are equipped with a residual heat removal device, which takes out the reactor water in the reactor pressure vessel and circulates it through a heat exchanger when the reactor is shut down, and removes the decay heat generated in the reactor core. It is configured to remove residual heat such as.

そして、従来この残留熱除去装置は第1図に示す如く構
成されていた。
Conventionally, this residual heat removal apparatus was constructed as shown in FIG.

すなわち、1は原子炉圧力容器であって、この原子炉圧
力容器1内には炉心(図示せず)が収容されている。
That is, 1 is a nuclear reactor pressure vessel, and a reactor core (not shown) is accommodated in this reactor pressure vessel 1.

また、2は原子炉再循環ポンプ、3は原子炉再循環管路
である。
Further, 2 is a reactor recirculation pump, and 3 is a reactor recirculation pipe.

そして、上記原子炉再循環管路3には炉水取出管路4が
分岐接続されており、炉水の一部を取出せるように構成
されている。
A reactor water take-off pipe 4 is branched and connected to the reactor recirculation pipe 3, so that a portion of the reactor water can be taken out.

そして、この炉水取出管路4を介して取出された炉水は
残留熱除去系ポンプ5によって残留熱除去系熱交換器6
に送られて冷却されるように構成されている。
The reactor water taken out through this reactor water take-out pipe line 4 is transferred to a residual heat removal system heat exchanger 6 by a residual heat removal system pump 5.
It is configured to be sent to and cooled.

そしてこの残留熱除去系熱交換器6によって冷却された
炉水の一部は炉水戻し管路7を介して原子炉再循環管路
3に戻され、また残りの炉水は炉水戻し管路8を介して
直接原子炉圧力容器1内に戻されるように構成されてい
る。
A part of the reactor water cooled by the residual heat removal system heat exchanger 6 is returned to the reactor recirculation line 3 via the reactor water return line 7, and the remaining reactor water is returned to the reactor water return line 3. It is configured to be returned directly into the reactor pressure vessel 1 via a line 8.

また1、才記炉水取出管路4にはプール水供給管路9が
分岐接続されており、このプール水供給管路9は原子炉
格納容器の圧力抑制プール10内に連通している。
1. A pool water supply pipe 9 is branched and connected to the reactor water take-off pipe 4, and this pool water supply pipe 9 communicates with the pressure suppression pool 10 of the reactor containment vessel.

また、上記炉水戻し管路8にはプール水戻し管路11が
分岐接続され、このプール水戻し管路11は上記の圧力
抑制プール10内に連通している。
Further, a pool water return pipe 11 is branched and connected to the reactor water return pipe 8, and this pool water return pipe 11 communicates with the pressure suppression pool 10 described above.

そして、原子炉の停止時等には上記のプール水供給管路
9の途中に設けられた開閉弁12およびプール水戻し管
路11の途中に設けられた開閉弁13を閉弁するととも
に炉水取出管路4の途中に設けられた開閉弁14および
炉水戻し管路7,8の途中に設けられた開閉弁15.1
6を開弁して残留熱除去系ポンプ5を運転し、残留熱除
去系熱交換器6を介して炉水を循環し、炉心で発生する
残留熱を除去する。
When the reactor is shut down, the on-off valve 12 provided in the middle of the pool water supply pipe 9 and the on-off valve 13 provided in the middle of the pool water return pipe 11 are closed, and the reactor water An on-off valve 14 provided in the middle of the extraction pipe 4 and an on-off valve 15.1 provided in the middle of the reactor water return pipes 7 and 8
6 is opened, the residual heat removal system pump 5 is operated, and reactor water is circulated through the residual heat removal system heat exchanger 6 to remove residual heat generated in the reactor core.

また、原子炉の運転時においてはこの残留熱除去装置は
長期間にわたって運転されないので、定期的にサーベイ
ランス運転と称する試験運転をおこない、その機能を確
認する。
Furthermore, since this residual heat removal device is not operated for a long period of time during operation of a nuclear reactor, a test operation called a surveillance operation is periodically performed to confirm its function.

そして、このようなサーベイランス運転の際には炉水を
循環することかできないので炉水取出管路4の開閉弁1
4および炉水戻し管路γ。
During such surveillance operations, the reactor water can only be circulated, so the on-off valve 1 of the reactor water take-out pipe 4 is closed.
4 and reactor water return pipe γ.

8の開閉弁15.16を閉弁しておくとともにプール水
供給管路9の開閉弁12およびプール水戻し管路11の
開閉弁13を開弁して残留熱除去系ポンプ5を運転し、
このプール水供給管路9およびプール水戻し管路11を
介して圧力抑制プール10内のプール水17を循環させ
、上記のサーベイランス運転をおこなう。
The on-off valves 15 and 16 of 8 are closed, and the on-off valve 12 of the pool water supply pipe 9 and the on-off valve 13 of the pool water return pipe 11 are opened to operate the residual heat removal system pump 5,
The pool water 17 in the pressure suppression pool 10 is circulated through the pool water supply pipe 9 and the pool water return pipe 11 to perform the above-mentioned surveillance operation.

そして、このサーベイランス運転が終了した後は炉水取
出管路4、残留熱除去系熱交換器6、炉水戻し管路7,
8等の内部に残ったプール水を排出せずにそのまま満水
状態としておき、これらの内面が空気に触れて酸化する
のを防止するいわゆる満水保管をおこなっている。
After this surveillance operation is completed, the reactor water take-out pipe 4, the residual heat removal system heat exchanger 6, the reactor water return pipe 7,
The pool water remaining inside the pools 8, etc. is left in a full state without being drained, and so-called full water storage is performed to prevent the inner surfaces of these pools from being exposed to air and oxidizing.

しかし、上記の圧力抑制プール10内のプール水17に
は一般に飽和状態に近い高濃度の溶存酸素が存在してお
り、上記の如き満水保管をおこなってもなおかつ炉水取
出管路4、残留熱除去系熱交換器6、炉水戻し管路7゛
、8等の内面に相当量の錆が発生する。
However, the pool water 17 in the pressure suppression pool 10 generally contains a high concentration of dissolved oxygen close to saturation, and even if the water is stored at full capacity as described above, the reactor water take-out pipe 4 still A considerable amount of rust occurs on the inner surfaces of the removal system heat exchanger 6, reactor water return pipes 7'', 8, etc.

そして、この錆は次の原子炉が停止してこの残留熱除去
装置が運転されると循環される炉水とともに原子炉圧力
容器1内に持ち込まれ、燃料棒の表面等に付着して燃料
の健全性に悪影響を与え、またこの錆が放射化されてい
わゆる放射性クラッドになる等の不具合があった。
When the next reactor shuts down and this residual heat removal device is operated, this rust is carried into the reactor pressure vessel 1 along with the circulating reactor water, adheres to the surfaces of the fuel rods, etc., and removes the fuel. There were other problems, such as having a negative impact on the soundness and the rust becoming radioactive and becoming so-called radioactive cladding.

本発明は以上の事情にもとづいてなされたものでその目
的とするところは停止保管時における配管内面等の錆の
発生がきわめて少なく、この錆による燃料の健全性への
悪影響や放射性クラッド等の発生量の低減することがで
きる残留熱除去装置を得ることにある。
The present invention has been made based on the above circumstances, and its purpose is to minimize the occurrence of rust on the inner surface of pipes, etc. during stoppage and storage, and to prevent the occurrence of adverse effects on the integrity of the fuel due to this rust and the occurrence of radioactive crud, etc. The object of the present invention is to obtain a residual heat removal device that can reduce the amount of residual heat.

以下本発明を第2図に示す一実施例にしたがつて説明す
る。
The present invention will be described below with reference to an embodiment shown in FIG.

図中101は原子炉圧力容器であって、この原子炉圧力
容器101内には炉心(図示せず)が収容されている。
In the figure, 101 is a reactor pressure vessel, and a reactor core (not shown) is accommodated within this reactor pressure vessel 101.

また、102は原子炉再循環ポンプ、103は原子炉再
循環管路である。
Further, 102 is a reactor recirculation pump, and 103 is a reactor recirculation pipe.

そして、上記原子炉再循環ポンプ102の吸込側の原子
炉再循環管路103には炉水取出管路104が分岐接続
され、上記原子炉再循環管路103を介して炉水が取出
されるように構成されている。
A reactor water extraction pipe 104 is branched and connected to the reactor recirculation pipe 103 on the suction side of the reactor recirculation pump 102, and reactor water is taken out through the reactor recirculation pipe 103. It is configured as follows.

そして、この炉水取出管路104の途中には開閉弁12
9が設けられているとともに残留熱除去系ポンプ105
の吸込側に連通され、取り出された炉水はこの残留熱除
去系ポンプ105によって残留熱除去系熱交換器106
に送られるように構成されている。
An on-off valve 12 is located in the middle of this reactor water extraction pipe 104.
9 and a residual heat removal system pump 105.
The extracted reactor water is transferred to the residual heat removal system heat exchanger 106 by this residual heat removal system pump 105.
is configured to be sent to.

そして、この残留熱除去系熱交換器106に送られた炉
水は外部から送られた冷却材と熱交換され、冷却される
ように構成されている。
The reactor water sent to the residual heat removal system heat exchanger 106 is configured to be cooled by exchanging heat with a coolant sent from the outside.

そしてこの残留熱除去系熱交換器106によって冷却さ
れた炉水の一部は炉水戻し管路107および開閉弁10
8を介して原子炉再循環ポンプ102の吐出側の原子炉
再循環管路103に戻され、また残りの炉水は炉水戻し
管路109および開閉弁110を介して直接原子炉圧力
容器101内に戻されるように構成されている。
A portion of the reactor water cooled by the residual heat removal system heat exchanger 106 is transferred to the reactor water return pipe 107 and the on-off valve 10.
8 to the reactor recirculation line 103 on the discharge side of the reactor recirculation pump 102, and the remaining reactor water is returned directly to the reactor pressure vessel 101 via the reactor water return line 109 and the on-off valve 110. It is configured to be placed back inside.

また、上記炉水取出管路104にはプール水供給管路1
11が分岐接続されており、このプール水供給管路11
1は原子炉格納容器の圧力抑制プール112内に連通し
ている。
In addition, the above-mentioned reactor water take-out pipe 104 includes a pool water supply pipe 1.
11 is branched and connected, and this pool water supply pipe 11
1 communicates with the pressure suppression pool 112 of the reactor containment vessel.

なお、このプール水供給管路111の途中には開閉弁1
13が設けられている。
Note that there is an on-off valve 1 in the middle of this pool water supply pipe 111.
13 are provided.

また、上記炉水戻し管路109の途中にはプール水戻し
管路114が分岐接続され、このプール水戻し管路11
4は上記圧力抑制室112に連通している。
Further, a pool water return pipe 114 is branched and connected in the middle of the reactor water return pipe 109, and this pool water return pipe 11
4 communicates with the pressure suppression chamber 112.

そして、このプール水戻し管路114の途中には開閉弁
115が設けられている。
An on-off valve 115 is provided in the middle of this pool water return pipe 114.

また、116は脱気水タンクであって、この脱気水タン
ク116内には所定量の脱気水117が貯溜されている
Further, 116 is a deaerated water tank, and a predetermined amount of deaerated water 117 is stored in this deaerated water tank 116.

そして、この脱気水タンク116には真空ポンプ118
が接続されており、この脱気水タンク116内を真空に
排気し、内部に貯溜されている水の中に溶解していを溶
存酸素等を脱気するように構成されている。
A vacuum pump 118 is installed in this deaerated water tank 116.
is connected to the degassed water tank 116, and is configured to evacuate the inside of this degassed water tank 116 and degas dissolved oxygen, etc. in the water stored inside.

そして、上記プール水供給管路111が分岐接続されて
いる箇所より上流側の箇所の炉水取出管路104には暖
気水供給管路119が分岐接続されており、この脱気水
供給管路119は上記脱気水タンク116に連通してい
る。
A warm air water supply pipe 119 is branch-connected to the reactor water take-off pipe 104 at a location upstream from the location where the pool water supply pipe 111 is branch-connected, and this deaerated water supply pipe 119 communicates with the degassed water tank 116.

そして、この脱気水供給管路119の途中には開閉弁1
20が設けられ、また脱気水タンク116内の脱気水1
17を上記炉水取出管路104に送る脱気水ポンプ12
1が設けられている。
An on-off valve 1 is provided in the middle of this deaerated water supply pipe 119.
20 is provided, and deaerated water 1 in the deaerated water tank 116 is provided.
17 to the reactor water extraction pipe 104.
1 is provided.

また、上記炉水戻し管路107,109には脱気水戻し
管路122゜123がそれぞれ分岐接続されており、こ
れら脱気水戻し管路122,123は1本の脱気水集合
戻し管路124にまとめられ、上記の脱気水タンク11
6に連通している。
Further, degassed water return pipes 122 and 123 are branched and connected to the reactor water return pipes 107 and 109, respectively, and these degassed water return pipes 122 and 123 are connected to one degassed water collection return pipe The degassed water tank 11
It is connected to 6.

そして、上記脱気水戻し管路122,123の途中には
それぞれ開閉弁126.127が設けられ、また脱気水
集合戻し管路124の途中にはこの管路内を流れる水の
溶存酸素濃度を測定する溶存酸素濃度検出器128が設
けられている。
On-off valves 126 and 127 are provided in the middle of the degassed water return pipes 122 and 123, respectively, and in the middle of the degassed water collection and return pipe 124, the concentration of dissolved oxygen in the water flowing through the pipe is provided. A dissolved oxygen concentration detector 128 is provided to measure the dissolved oxygen concentration.

以上の如く構成された本発明の一実施例は、原子炉停止
時等には炉水取出管104の開閉弁12g。
In one embodiment of the present invention configured as described above, the on-off valve 12g of the reactor water outlet pipe 104 is used when the reactor is shut down.

炉水戻し管路107,109の開閉弁108゜110を
開弁するとともにプール水供給管路111の開閉弁11
3、プール水戻し管路114の開閉弁115脱気水供給
管路119の開閉弁120および脱気水戻し管路122
,123の開閉弁126゜127をそれぞれ閉弁して残
留熱除去系ポンプ105を運転する。
The on-off valves 108 and 110 of the reactor water return pipes 107 and 109 are opened, and the on-off valve 11 of the pool water supply pipe 111 is opened.
3. On-off valve 115 of pool water return pipe 114, on-off valve 120 of deaerated water supply pipe 119, and deaerated water return pipe 122
, 123 are closed, and the residual heat removal system pump 105 is operated.

したがって炉水は炉水取出管路104、残留熱除去系熱
交換器106、炉水戻し管路107,109を介して循
環され、炉心で発生する崩壊熱等の残留熱を除去する。
Therefore, the reactor water is circulated through the reactor water take-off pipe 104, the residual heat removal system heat exchanger 106, and the reactor water return pipes 107 and 109 to remove residual heat such as decay heat generated in the reactor core.

そして、原子炉運転時等においては炉水取出管路104
の開閉弁129および炉水戻し管路107,109の開
閉弁108,110を閉弁するとともにプール水供給管
路111の開閉弁113およびプール水戻し管路114
の開閉弁115を開弁し、残留熱除去系ポンプ105を
運転して圧力抑制プール112内のプール水130を循
環し、この残留熱除去装置のサーベイランス運転をおこ
なう。
During reactor operation, the reactor water extraction pipe 104
and the on-off valves 108 and 110 of the reactor water return pipes 107 and 109 are closed, and the on-off valve 113 of the pool water supply pipe 111 and the pool water return pipe 114 are closed.
The on-off valve 115 is opened, the residual heat removal system pump 105 is operated to circulate the pool water 130 in the pressure suppression pool 112, and a surveillance operation of this residual heat removal device is performed.

そして、このサーベイランス運転が終了したらプール水
供給管路111の開閉弁113、プール水戻し管路11
4の開閉弁115を閉弁するとともに脱気水供給管路1
19の開閉弁120および脱気水戻し管路122,12
3の開閉弁126,127を開弁して脱気水ポンプ12
1および残留熱除去系ポンプ105を運転して脱気水タ
ンク116内の脱気水117を循環させる。
When this surveillance operation is completed, the on-off valve 113 of the pool water supply pipe 111, the pool water return pipe 11
The on-off valve 115 of No. 4 is closed and the degassed water supply pipe 1 is closed.
19 on-off valve 120 and deaerated water return pipes 122, 12
Open the on-off valves 126 and 127 of 3 to deaerate water pump 12.
1 and the residual heat removal system pump 105 are operated to circulate the degassed water 117 in the degassed water tank 116.

したがって、上記炉水取出管路104、残留熱除去系熱
交換器106および炉水戻し管路107,109内に残
留しているプール水130は溶存酸素濃度の小さな脱気
水117で置換される。
Therefore, the pool water 130 remaining in the reactor water take-out pipe 104, residual heat removal system heat exchanger 106, and reactor water return pipes 107, 109 is replaced with degassed water 117 with a low dissolved oxygen concentration. .

そして、上記残留しているプール水130が完全に脱気
水117で置換されたら開閉弁120,126,127
を閉弁し、炉水取出管路104、残留熱除去系熱交換器
106および炉水戻し管ml 07 、10.9内に脱
気水を充満した状態で満水保管する。
When the remaining pool water 130 is completely replaced with deaerated water 117, the on-off valves 120, 126, 127
The reactor water take-off pipe 104, the residual heat removal system heat exchanger 106, and the reactor water return pipes ml 07 and 10.9 are filled with degassed water and stored at full capacity.

そして、この脱気水117はその溶存酸素a度が低いの
で、保管中にこれらの内面で錆が発生することが防止さ
れる。
Since this degassed water 117 has a low dissolved oxygen degree, rust is prevented from forming on these inner surfaces during storage.

なお、この一実施例では脱気水集合戻し管路124に溶
存酸素濃度検出器128が設けられているので、この溶
存酸素濃度検出器128によって脱気水集合戻し管路1
24内を流れる水の溶存酸素濃度を測定監視することに
よってプール水130が脱気水117て完全に置換され
たか否かを検知できる。
In this embodiment, since the dissolved oxygen concentration detector 128 is provided in the degassed water collection and return pipe 124, the dissolved oxygen concentration detector 128 allows the degassed water collection and return pipe 1 to be detected.
By measuring and monitoring the dissolved oxygen concentration of the water flowing through the pool 24, it is possible to detect whether the pool water 130 has been completely replaced by the degassed water 117.

また脱気水供給管路119はプール水供給管路111の
分岐接続箇所よりも上流側で炉水取出管路104に分岐
接続され、また脱気水戻し管路122,123はプール
水戻し管路114の分岐接続箇所より下流側で炉水戻し
管路107゜109に分岐接続されているので、残留し
たプール水130を残すことなく完全に脱気水117で
置換できる。
Further, the degassed water supply pipe 119 is branched and connected to the reactor water take-out pipe 104 on the upstream side of the branch connection point of the pool water supply pipe 111, and the degassed water return pipes 122 and 123 are pool water return pipes. Since the reactor water return pipes 107 and 109 are connected to the reactor water return pipes 107 and 109 on the downstream side of the branch connection point of the line 114, the remaining pool water 130 can be completely replaced with the degassed water 117 without leaving any residue.

上述の如く本発明は脱気水を貯溜する脱気水タンクを設
け、この脱気水を炉水取出管路に供給する脱気水供給管
路と炉水戻し管路から脱気水を8J’e気水クンクに戻
す脱気水戻し管路とを設けたものである。
As described above, the present invention provides a deaerated water tank for storing deaerated water, and supplies 8 J of deaerated water from the deaerated water supply line and the reactor water return line that supply this deaerated water to the reactor water take-out line. 'e A degassed water return pipe is provided to return the air and water to the tank.

したがって圧力抑制プール内のプール水を用いてこの残
留熱除去装置のサーベイランス運転をおこなった後上記
脱気水供給管路および脱気水戻し管路を介して脱気水タ
ンク内の脱気水を循環し、残留した溶存酸素濃度の高い
プール水を溶存酸素濃度の低い脱気水で置換して満水保
管することができる。
Therefore, after conducting a surveillance operation of this residual heat removal device using the pool water in the pressure suppression pool, the degassed water in the degassed water tank is supplied via the degassed water supply pipe and the degassed water return pipe. The remaining pool water with a high dissolved oxygen concentration can be replaced with degassed water with a low dissolved oxygen concentration and stored at full capacity.

また、脱気水供給管路はプール水供給管路の分岐接続箇
所よりも上流側で炉水取出管路に分岐接続され、また脱
気水戻し管路はプール水戻し管路の分岐接続箇所より下
流側で炉水戻し管路に分岐接続されているので、残留し
たプール水を残すことなく完全に脱気水で置換できる。
In addition, the degassed water supply pipe is branched and connected to the reactor water take-out pipe on the upstream side of the branch connection point of the pool water supply pipe, and the deaerated water return pipe is branched and connected to the pool water return pipe branch connection point. Since it is branched and connected to the reactor water return pipe on the downstream side, it is possible to completely replace residual pool water with degassed water without leaving any residual pool water.

したがって保管中において炉水取出管路、残留熱除去系
熱交換器、炉水戻し管路等の内面に錆が発生することが
防止され、このような錆が原子炉圧力容器内−に持込ま
れることによる燃料の健全性への悪影響や放射性クラッ
ドの発生量の増加等の不具合を有効に防止できる等その
効果は犬である。
Therefore, rust is prevented from forming on the inner surfaces of the reactor water take-out pipe, residual heat removal system heat exchanger, reactor water return pipe, etc. during storage, and such rust is carried into the reactor pressure vessel. Its effects are outstanding, such as being able to effectively prevent problems such as adverse effects on the integrity of the fuel and an increase in the amount of radioactive crud generated.

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

第1図は従来例の概略系統図、第2図は本発明の一実施
例の概略系統図である。 101・・・・・・原子炉圧力容器、104・・・・・
・炉水取出管路、105・・・・・・残留熱除去系ポン
プ、106・・・・・・残留熱除去系熱交換器、107
,109・・・・・・炉水戻し管路、112・・・・・
・圧力抑制プール、111・・・・・・プール水供給管
路、114・・・・・・プール水戻し管路、116・・
・・・・脱気水タンク、117・・・・・・脱気水、1
19・・・・・・脱気水供給管路、122,123・・
・・・・脱気水戻し管路。
FIG. 1 is a schematic system diagram of a conventional example, and FIG. 2 is a schematic system diagram of an embodiment of the present invention. 101... Reactor pressure vessel, 104...
・Reactor water extraction pipe, 105...Residual heat removal system pump, 106...Residual heat removal system heat exchanger, 107
, 109... Reactor water return pipe, 112...
- Pressure suppression pool, 111...Pool water supply pipe, 114...Pool water return pipe, 116...
...Deaerated water tank, 117... Deaerated water, 1
19... Degassed water supply pipe, 122, 123...
...Deaerated water return pipe.

Claims (1)

【特許請求の範囲】[Claims] 1 残留熱除去系ポンプと、この残留熱除去系ポンプの
吸込側と原子炉圧力容器内とを連通し上記原子炉圧力容
器内の炉水を取出して上記残留熱除去系ポンプに供給す
る炉水取出管路と上記残留熱除去系ポンプによって送ら
れた炉水を冷却する残留熱除去系熱交換器と、この残留
熱除去系熱交換器で冷却された炉水を上記原子炉圧力容
器内に戻す炉水戻し管路と、上記炉水取出管路に分岐接
続されるとともに原子炉格納容器の圧力抑制プール内に
連通しこの圧力抑制プール内のプール水を上記残留熱除
去系ポンプに供給するプール水供給管路と、上記炉水戻
し管路に分岐接続されるとともに上記圧力抑制プール内
に連通しプール水を圧力抑制プール内に戻すプール水戻
し管路と、脱気水を貯溜する脱気水クンクと、この脱気
水タンク内を真空に排気して内部に貯溜されている水を
脱気する真空ポンプと、上記プール水供給管路の分岐接
続箇所より上流側の箇所で上記炉水取出管路に分岐接続
されるとともに上記脱気水クンク内に連通しこの脱気水
タンク内の脱気水を上記残留熱除去系ポンプに供給する
脱気水供給管路と、上記プール水戻し管路の分岐接続箇
所より下流側の箇所で上記炉水戻し管路に分岐接続され
るとともに上記脱気水タンク内に連通し脱気水を上記脱
気水タンク内に戻す脱気水戻し管路とを具備したことを
特徴とする残留熱除去装置。
1. A residual heat removal system pump, which communicates the suction side of the residual heat removal system pump with the inside of the reactor pressure vessel to extract reactor water from the reactor pressure vessel and supply it to the residual heat removal system pump. A residual heat removal system heat exchanger that cools the reactor water sent by the extraction pipe and the residual heat removal system pump, and a residual heat removal system heat exchanger that cools the reactor water cooled by the residual heat removal system heat exchanger into the above reactor pressure vessel. The reactor water return pipe is branch-connected to the reactor water take-out pipe and communicated with the pressure suppression pool of the reactor containment vessel, and supplies the pool water in the pressure suppression pool to the residual heat removal system pump. a pool water supply pipe, a pool water return pipe that is branch-connected to the reactor water return pipe and communicates with the pressure suppression pool to return pool water to the pressure suppression pool; and a pool water return pipe that stores deaerated water. A vacuum pump that evacuates the inside of this deaerated water tank and deaerates the water stored inside, and the above-mentioned furnace at a point upstream from the branch connection point of the pool water supply pipe. A degassed water supply pipe that is branch-connected to the water take-out pipe and communicates with the degassed water tank and supplies the degassed water in the degassed water tank to the residual heat removal system pump, and the pool water A degassed water return branch is connected to the reactor water return pipe at a point downstream from the branch connection point of the return pipe and communicates with the degassed water tank to return the degassed water to the degassed water tank. A residual heat removal device characterized by comprising a pipe line.
JP55177489A 1980-12-16 1980-12-16 Residual heat removal equipment Expired JPS5939720B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP55177489A JPS5939720B2 (en) 1980-12-16 1980-12-16 Residual heat removal equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP55177489A JPS5939720B2 (en) 1980-12-16 1980-12-16 Residual heat removal equipment

Publications (2)

Publication Number Publication Date
JPS57100388A JPS57100388A (en) 1982-06-22
JPS5939720B2 true JPS5939720B2 (en) 1984-09-26

Family

ID=16031788

Family Applications (1)

Application Number Title Priority Date Filing Date
JP55177489A Expired JPS5939720B2 (en) 1980-12-16 1980-12-16 Residual heat removal equipment

Country Status (1)

Country Link
JP (1) JPS5939720B2 (en)

Also Published As

Publication number Publication date
JPS57100388A (en) 1982-06-22

Similar Documents

Publication Publication Date Title
US6795518B1 (en) Integral PWR with diverse emergency cooling and method of operating same
EP0418701B1 (en) Reactor core decay heat removing system in a pressurized water reactor
US4647425A (en) Method of vacuum degassing and refilling a reactor coolant system
US3419467A (en) Method of and apparatus for locating envelope-tube damage at individual nuclear fuel elements in a reactor core
US4075060A (en) Method for removing fission products from a nuclear reactor coolant
US3910817A (en) Method and apparatus for removing radioactive gases from a nuclear reactor
JPS5939720B2 (en) Residual heat removal equipment
JP2548838B2 (en) Core collapse heat removal system for pressurized water reactor
US5517539A (en) Method of decontaminating a PWR primary loop
JPS60100794A (en) Pressurized water reactor equipment
US4204911A (en) Method and apparatus for removing iodine from a nuclear reactor coolant
JP2772053B2 (en) Vent apparatus for reactor containment vessel and method for reducing internal pressure
JP3130095B2 (en) Method and apparatus for removing decay heat of boiling water reactor
JPH0440397A (en) Nuclear reactor pressure vessel cooling device
JPH06214081A (en) Vent device for nuclear reactor containment vessel
JPS6223840B2 (en)
Higby et al. CONCEPTUAL SYSTEM DESIGN DESCRIPTION FOR THE SODIUM RECEIVING AND PROCESSING SYSTEM. VOLUME 81.
Wolters et al. The significance of water ingress accidents in small HTRs
JPS5941155B2 (en) Reactor shutdown cooling system
JPH0271193A (en) Nuclear reactor containment vessel
JPS5877698A (en) Flashing device for reactor residual heat removable system
JPS631276Y2 (en)
JPS6031092A (en) Container for nuclear reactor
JPS59112293A (en) Leaked sea water decontaminating device
JPS6243597A (en) Shipping device