JPS5915891A - Cooling circuit for reactor equipment - Google Patents

Cooling circuit for reactor equipment

Info

Publication number
JPS5915891A
JPS5915891A JP57125362A JP12536282A JPS5915891A JP S5915891 A JPS5915891 A JP S5915891A JP 57125362 A JP57125362 A JP 57125362A JP 12536282 A JP12536282 A JP 12536282A JP S5915891 A JPS5915891 A JP S5915891A
Authority
JP
Japan
Prior art keywords
seawater
heat exchanger
intermediate loop
temperature side
loop
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
JP57125362A
Other languages
Japanese (ja)
Inventor
糸矢 清広
滝沢 洋二
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
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Nippon Genshiryoku Jigyo KK
Tokyo Shibaura Electric Co Ltd
Nippon Atomic Industry Group 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 Nippon Genshiryoku Jigyo KK, Tokyo Shibaura Electric Co Ltd, Nippon Atomic Industry Group Co Ltd filed Critical Nippon Genshiryoku Jigyo KK
Priority to JP57125362A priority Critical patent/JPS5915891A/en
Publication of JPS5915891A publication Critical patent/JPS5915891A/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
    • 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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  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (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】 [発明の技術分野J 本発明は原子炉機器冷却系に関する。[Detailed description of the invention] [Technical field of invention J The present invention relates to a nuclear reactor equipment cooling system.

1発明の技術的背量] 一般に沸騰水形原子炉のような軽水形原子炉Cは、炉心
で発生した熱を除去づるために原子炉機器冷却系が配設
されている。
1. Technical burden of the invention] In general, a light water nuclear reactor C such as a boiling water reactor is provided with a reactor equipment cooling system to remove heat generated in the reactor core.

この原子炉機器冷却系I系は原子炉冷Ml拐喪失事故時
または通常運転時等の種々の運転モードに対しC使用さ
れており、具体的には例えば、以下のような機能を有し
でいる。
This reactor equipment cooling system I system is used for various operation modes such as during a reactor cold Ml loss accident or during normal operation.Specifically, it has the following functions. There is.

(1)冷却材喪失事故時に他の非常用炉心冷却系ととも
に働き、炉水位の回復とその紐持を行ない燃料被覆管の
破損を防ぐ。
(1) In the event of a loss of coolant accident, it works together with other emergency core cooling systems to restore and maintain the reactor water level and prevent damage to the fuel cladding.

(2)燃料取替えやその他の作業がぐぎるように崩壊熱
および残留物を取除く。
(2) Remove decay heat and residue to facilitate fuel replacement and other operations.

(3)スクラム時に炉蒸気を直接凝縮する。(3) Direct condensation of furnace steam during scram.

(4)冷却材喪失事故時に圧力抑制室で完全に蒸気を凝
縮rきるように圧力抑−リ室を冷却する。
(4) Cool the pressure suppression chamber so that steam can be completely condensed in the pressure suppression chamber in the event of a loss of coolant accident.

(5)燃料プールおよび格納容器プール冷fj′I装置
に大ぎな負荷がかかった場合にはこれらを補助する。
(5) Assist the fuel pool and containment pool cooling fj'I equipment when a large load is placed on them.

第1図はこのような、従来の原子炉機器冷却系を示すも
ので、図において符@1は残留熱除去熱交換器を示して
いる。この残留熱除去熱交換器1の高温側には原子炉−
次冷却水ループ2が接続されている。
FIG. 1 shows such a conventional nuclear reactor equipment cooling system, and in the figure, the symbol @1 indicates a residual heat removal heat exchanger. The high temperature side of this residual heat removal heat exchanger 1 is equipped with a nuclear reactor.
A secondary cooling water loop 2 is connected.

残留熱除去熱交換器1の低温側は中間ループ3により2
台の中間ループ熱交換器4a 、4bに接続されており
、さらに2台の中間ループ熱交換器4a 、4bは海水
ループ5により尚水取込口5a。
The low temperature side of the residual heat removal heat exchanger 1 is connected to the 2
The two intermediate loop heat exchangers 4a and 4b are connected to a fresh water intake port 5a through a seawater loop 5.

6bおよび海水放出ロアに接続されている。6b and the seawater discharge lower.

すなわち海水取込口5a 、5bから海水ポンプ8a1
8bに吸込まれた海水は、開閉弁9a、9bおよび、開
閉弁10a、10bを通り中間ループ熱交換器4a、4
bで熱交換した後、開閉弁11a、11bを通り海水放
出ロアから海に放出される。
That is, from the seawater intake ports 5a and 5b, the seawater pump 8a1
The seawater sucked into 8b passes through on-off valves 9a, 9b and on-off valves 10a, 10b, and then enters intermediate loop heat exchangers 4a, 4.
After exchanging heat at step b, it passes through the on-off valves 11a and 11b and is discharged into the sea from the seawater discharge lower.

一方、中間ループ熱交換器4a 、4bの高温側で海水
と熱交換された中間ループ3の冷却水は、開閉弁12a
、12b1開閉弁13a、13b。
On the other hand, the cooling water of the intermediate loop 3, which has been heat exchanged with seawater on the high temperature side of the intermediate loop heat exchangers 4a and 4b, is transferred to the on-off valve 12a.
, 12b1 on-off valves 13a, 13b.

中間ループ循環ポンプ14a、14bおよび開閉弁15
a、15bを通った後残留熱除去熱交換器1の低温側に
流入し、原子炉−次冷却水ループ2内の冷却水と熱交換
され、開閉弁16、開閉弁17a、17bを通り中間ル
ープ熱交換器4a14b内に再循環する。
Intermediate loop circulation pumps 14a, 14b and on-off valve 15
After passing through a and 15b, it flows into the low temperature side of the residual heat removal heat exchanger 1, where it is heat exchanged with the cooling water in the sub-reactor cooling water loop 2, passes through the on-off valve 16, on-off valves 17a and 17b, and then flows into the intermediate Recirculated into loop heat exchanger 4a14b.

一般にこのような原子炉機器冷却系は、発電プラント内
に2系統配設されているが、例えば片方の系統に配設さ
れる2台の中間ループ循環ポンプ1.4a、14bまた
は海水ポンプ8a 、8bが何らかの原因により同時に
トリップした場合には、残りの1系統の残留熱除去熱交
換器1しか運転できなくなる。
Generally, two such reactor equipment cooling systems are installed in a power plant, and for example, two intermediate loop circulation pumps 1.4a and 14b or a seawater pump 8a, which are installed in one system, 8b trip at the same time for some reason, only the remaining residual heat removal heat exchanger 1 can be operated.

そして、この状態で、例えば原子炉機器冷却装置が作動
した場合には、高温待機運転において残留熱除去熱交換
器1を1台しか運転することができず、例えば、炉蒸気
を十分凝縮することができなくなる。また、この場合に
は、圧力抑制室の温度上昇が限界に近付いても残留熱除
去熱交換器1は炉蒸気凝縮モードで使用されているため
圧力抑制室冷却モードでの運転ができなくなるおそれが
ある。
In this state, for example, if the reactor equipment cooling system is activated, only one residual heat removal heat exchanger 1 can be operated in high-temperature standby operation, and for example, it is difficult to sufficiently condense the reactor steam. become unable to do so. In this case, even if the temperature rise in the pressure suppression chamber approaches its limit, the residual heat removal heat exchanger 1 is used in the furnace steam condensation mode, so there is a risk that it will not be able to operate in the pressure suppression chamber cooling mode. be.

[発明の目的] 本発明はかかる従来の事情に対処してなされたものCX
原子炉機器冷却系内に配設される中間ループ循環ポンプ
14a、14bまたは海水ポンプ8a 、8bのトリッ
プ時にも原子炉機器冷却系の機能を十分発揮することの
できる原子炉機器冷却系を提供しようとするものである
[Object of the invention] The present invention has been made in response to such conventional circumstancesCX
It is an object of the present invention to provide a reactor equipment cooling system that can fully demonstrate the functions of the reactor equipment cooling system even when the intermediate loop circulation pumps 14a, 14b or seawater pumps 8a, 8b installed in the reactor equipment cooling system trip. That is.

[発明の概要] すなわち本発明は、海水ポンプにより吸引された海水を
中間ループ熱交換器の低温側に循環させる海水ループと
、前記中間ループ熱交換器の高温側と残留熱除去熱交換
器の低温側との間に中間ループ循環ポンプにより冷却水
を循環させる中間ループと、前記海水ポンプで吸引され
た海水を前記海水ポンプまたは中間ループ循環ポンプの
いずれか一方を介して前記残留熱除去熱交換器の低温側
に流入させる開閉弁の介挿される吸込バイパスラインと
、前記残留熱除去熱交換器の低温側に流入した前記海水
を海水放出口から海水中に放出する放出バイパスライン
とからなることを特徴とする原子炉機器冷却系である。
[Summary of the Invention] That is, the present invention provides a seawater loop that circulates seawater sucked by a seawater pump to the low-temperature side of an intermediate loop heat exchanger, and a high-temperature side of the intermediate loop heat exchanger and a residual heat removal heat exchanger. An intermediate loop that circulates cooling water between the low temperature side and the intermediate loop circulation pump, and the residual heat removal heat exchange through which the seawater sucked by the seawater pump is passed through either the seawater pump or the intermediate loop circulation pump. consisting of a suction bypass line into which an on-off valve is inserted that allows the flow to flow into the low temperature side of the heat exchanger, and a discharge bypass line that discharges the seawater that has flowed into the low temperature side of the residual heat removal heat exchanger into the seawater from the seawater outlet. This is a nuclear reactor equipment cooling system characterized by:

[発明の実施例] 以下本発明の詳細を第2図に示す一実施例について説明
する。なお第2図において第1図と共通する部分には同
一符号が付されている。
[Embodiment of the Invention] The details of the present invention will be described below with reference to an embodiment shown in FIG. In FIG. 2, parts common to those in FIG. 1 are given the same reference numerals.

第2図は本発明の一実施例の原子炉機器冷却系を示すも
ので、海水取込口6aと海水ポンプ8aとの間および中
間ループ3の開閉弁15a、15bと残留熱除去熱交換
器1低温側流入口との間を接続して吸込バイパスライン
18が配設されており、この吸込バイパスライン18に
は海水取込ロ6a側から順に海水吸込バイパス弁19お
よび吸込バイパス弁20が介挿されている。そして海水
ループ5の開閉弁9a 、9bと開閉弁10a、1ob
との間と、吸込バイパスライン18の海水吸込バイパス
弁19と吸込バイパス弁20との間を接続して海水補助
ライン弁21の介挿される海水補助ライン22が接続さ
れており、また中間ループ3の開閉弁12a、12b、
!:開閉弁13a、13bとの間と、吸込バイパスライ
ン18の海水吸込バイパス弁19と吸込バイパス弁2o
との間を接続して中間補助ライン弁23の介挿される中
間補助ライン24が配設されている。
FIG. 2 shows a reactor equipment cooling system according to an embodiment of the present invention, and shows the on-off valves 15a and 15b between the seawater intake port 6a and the seawater pump 8a, the intermediate loop 3, and the residual heat removal heat exchanger. 1. A suction bypass line 18 is provided to connect the low temperature side inlet, and a seawater suction bypass valve 19 and a suction bypass valve 20 are interposed in this suction bypass line 18 in order from the seawater intake lobe 6a side. It is inserted. On-off valves 9a, 9b and on-off valves 10a, 1ob of the seawater loop 5
A seawater auxiliary line 22 into which a seawater auxiliary line valve 21 is inserted is connected between the seawater suction bypass valve 19 and the suction bypass valve 20 of the suction bypass line 18, and a seawater auxiliary line 22 in which a seawater auxiliary line valve 21 is inserted is connected. On-off valves 12a, 12b,
! : Between the on-off valves 13a and 13b, and between the seawater suction bypass valve 19 and the suction bypass valve 2o of the suction bypass line 18.
An intermediate auxiliary line 24, into which an intermediate auxiliary line valve 23 is inserted, is arranged to connect between the two.

そして、さらに、中間ループ3の開閉弁16と残留熱除
去熱交換器1低渇出口側と、海水ループ5の開閉弁11
a、11bと海水放出ロアとの間を接続して放出バイパ
ス弁25の配設される放出バイパスライン26が接続さ
れている。
Furthermore, the on-off valve 16 of the intermediate loop 3, the low-drainage outlet side of the residual heat removal heat exchanger 1, and the on-off valve 11 of the seawater loop 5
A discharge bypass line 26, in which a discharge bypass valve 25 is disposed, is connected between the seawater discharge lower portions a and 11b and the seawater discharge lower.

なお、以上述べた以外は第1図と同様に構成されでいる
ので、同一部分には同一符号を付して説明を省略する。
It should be noted that since the structure is the same as that shown in FIG. 1 except as described above, the same parts are given the same reference numerals and the explanation will be omitted.

以上のように構成された原子炉機器冷却系では、例えば
海水ポンプ8a 、8bが2台とも起動に失敗した場合
には、海水吸込バイパス弁19、中間補助ライン弁23
および放出バイパス弁25が開とされ、海水は海水取込
口6aから吸引された後、海水吸込バイパス弁19の配
設される吸込バイパスライン18を通り中間補助ライン
弁23の配設される中間補助ライン24を通った後、開
閉弁13a、13b、中間ループ循環ポンプ14a、1
4bおよび開閉弁15a、15bを通り残留熱除去熱交
換器1の低温流入側から残留熱除去熱交換器1内に流入
し、原子炉−次冷却水ループ2内の冷却水と熱交換した
後、放出バイパス弁25の配設される放出バイパスライ
ン26を通り海水放出ロアから海に放出される。従って
2台の海水ポンプ8a 、 8bが同時に起動失敗した
としても残留熱除去熱交換器1の機能が損われることは
ない。
In the reactor equipment cooling system configured as described above, for example, if both seawater pumps 8a and 8b fail to start, the seawater suction bypass valve 19 and the intermediate auxiliary line valve 23
Then, the discharge bypass valve 25 is opened, and after the seawater is sucked from the seawater intake port 6a, it passes through the suction bypass line 18 where the seawater suction bypass valve 19 is installed, and the intermediate auxiliary line valve 23 is installed. After passing through the auxiliary line 24, on-off valves 13a, 13b, intermediate loop circulation pumps 14a, 1
4b and on-off valves 15a and 15b, and flows into the residual heat removal heat exchanger 1 from the low-temperature inlet side of the residual heat removal heat exchanger 1, and after exchanging heat with the cooling water in the reactor-subcooling water loop 2. , and is discharged into the sea from the seawater discharge lower through a discharge bypass line 26 in which a discharge bypass valve 25 is disposed. Therefore, even if the two seawater pumps 8a and 8b fail to start at the same time, the function of the residual heat removal heat exchanger 1 will not be impaired.

また、以上のように構成された原子炉機器冷却系では、
中間ループ循環ポンプ14.a、14bが同時に起動に
失敗した場合には海水補助ライン弁21、吸込バイパス
弁20および放出バイパス弁25が開とされ、海水ポン
プ8a 、8bにより海水取込口6a 、6bから吸引
された海水は海水補助ライン22を通り吸込バイパスラ
イン18を通った後、残留熱除去熱交換器1の低温側流
入口から残留熱除去熱交換器1内に流入し、原子炉−次
冷却水ループ2内の冷却水を冷却し、放出バイパス弁2
5の配設される放出バイパスライン26を通り海水放出
ロアから海に放出される。従って中間ループ循環ポンプ
14a、14bが2台同時に故障したとしても残留熱除
去熱交換器1の冷却機能が損われることはない。
In addition, in the reactor equipment cooling system configured as above,
Intermediate loop circulation pump 14. a and 14b fail to start at the same time, the seawater auxiliary line valve 21, suction bypass valve 20, and discharge bypass valve 25 are opened, and the seawater pumps 8a and 8b suck seawater from the seawater intake ports 6a and 6b. After passing through the seawater auxiliary line 22 and the suction bypass line 18, it flows into the residual heat removal heat exchanger 1 from the low temperature side inlet of the residual heat removal heat exchanger 1, and flows into the reactor-subcooling water loop 2. Cooling water of the discharge bypass valve 2
The seawater is discharged into the sea from the seawater discharge lower through the discharge bypass line 26 provided in No. 5. Therefore, even if two intermediate loop circulation pumps 14a and 14b fail at the same time, the cooling function of the residual heat removal heat exchanger 1 will not be impaired.

第3図は、このように構成された原子炉機器冷却系の各
種弁を自動開閉し、中間ループ循環ポンプ14a、14
bおよび海水ポンプ8a 、 8bの故障時等にも原子
炉機器冷却系を正常に機能させる制御装置を示すもので
、この制御装置は入力装置27、監視装置28および表
示装置29とから構成されている。
FIG. 3 shows the automatic opening and closing of various valves in the reactor equipment cooling system configured as described above, and the intermediate loop circulation pumps 14a, 14.
This shows a control device that allows the reactor equipment cooling system to function normally even in the event of a failure of the reactor pumps 8a and 8b and the seawater pumps 8a and 8b. There is.

すなわち、入力装置27は原子炉機器冷却系内に配設さ
れるすべての開閉弁からこの開閉弁の開閉状態を示す信
号を入力し、また中間ループ循環ポンプ14a、14b
および海水ポンプ8a18bからこれらの作動状態を示
す信号を入力する。
That is, the input device 27 inputs signals indicating the open/closed states of all the on-off valves disposed in the reactor equipment cooling system, and also inputs signals indicating the open/closed states of the on-off valves disposed in the reactor equipment cooling system, and also inputs signals indicating the open/closed states of the on-off valves disposed in the reactor equipment cooling system.
and signals indicating these operating states are input from the seawater pump 8a18b.

監視袋ff128は入力装置27に入力された信号を入
力し、これらの信号状態を常時監視し、異常事態が発生
した場合にはどの開閉弁を開閉するかを判断する。そし
てこの監視装置28は異常信号とともに、開閉すべき開
閉弁の信号および開閉動作を行なった開閉弁の信号を表
示装置29に出力する。表示装置29はこれらの信号を
入力してこれらを表示する。
The monitoring bag ff128 inputs the signals input to the input device 27, constantly monitors the state of these signals, and determines which on-off valve should be opened or closed when an abnormal situation occurs. The monitoring device 28 outputs to the display device 29, together with the abnormality signal, signals of the on-off valves to be opened and closed and signals of the on-off valves that have been opened and closed. The display device 29 receives these signals and displays them.

第4図は監視装置28の海水ループ監視ロジックを示す
もので、この監視1」シックでは、例えば、海水ポンプ
Ba 、Bbの起動および開閉弁9a、9b、10a、
10b、lla、11bの開閉がそれぞれ判断され、例
えば海水ポンプ8aが起動していない場合で開閉弁9b
が閉とされている場合には、図に示すようにOR回路、
AND回路そしてOR回路を通り最終的に開閉弁19.
20.25が開とされ、残留熱除去熱交換器1の海水に
よる冷却が行なわれる。
FIG. 4 shows the seawater loop monitoring logic of the monitoring device 28. In this monitoring 1", for example, starting the seawater pumps Ba, Bb, opening/closing valves 9a, 9b, 10a,
10b, lla, and 11b are respectively determined, and for example, when the seawater pump 8a is not activated, the opening/closing valve 9b
is closed, the OR circuit as shown in the figure,
Finally, the on-off valve 19. passes through an AND circuit and an OR circuit.
20.25 is opened, and the residual heat removal heat exchanger 1 is cooled by seawater.

第5図は監視装置28の中間ループ監視ロジックを示す
もので、この監視ロジックでは、例えば、中間ループ循
環ポンプ14a、14bの起動状態および開閉弁12a
、12b113a、13b。
FIG. 5 shows the intermediate loop monitoring logic of the monitoring device 28. In this monitoring logic, for example, the activation state of the intermediate loop circulation pumps 14a, 14b and the opening/closing valve 12a are determined.
, 12b113a, 13b.

15a、15b、16.17a、17bの開閉状態が判
断され、例えば中間ループ循環ポンプ14bが起動しな
い場合で開閉弁13aが閉の場合に信号が出力され、O
R回路、AND回路およびOR回路を通り最終的に開閉
弁2’0,21.25が開とされる。すなわちこの場合
には海水ポンプ8a、8bにより直接海水が残留熱除去
熱交換器1に導かれ、残留熱除去熱交換器1の機能が維
持される。
The open/close states of 15a, 15b, 16.17a, and 17b are determined. For example, if the intermediate loop circulation pump 14b does not start and the on-off valve 13a is closed, a signal is output, and the O
It passes through the R circuit, the AND circuit, and the OR circuit, and finally the on-off valves 2'0, 21.25 are opened. That is, in this case, seawater is directly guided to the residual heat removal heat exchanger 1 by the seawater pumps 8a and 8b, and the function of the residual heat removal heat exchanger 1 is maintained.

[発明の効果コ 以上述べたように本発明の原子炉機器冷却系によれば、
中間ループ循環ポンプまたは海水ポンプに異常が生じた
場合にも、海水を直接残留熱除去熱交換器内に導くこと
により原子炉機器冷却系の機能を維持することができ、
原子炉機器冷却系の信頼性を大幅に向上することができ
る。
[Effects of the Invention] As described above, according to the reactor equipment cooling system of the present invention,
Even if an abnormality occurs in the intermediate loop circulation pump or seawater pump, the functionality of the reactor equipment cooling system can be maintained by directly guiding seawater into the residual heat removal heat exchanger.
The reliability of the reactor equipment cooling system can be significantly improved.

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

第1図は従来の原子炉機器冷却系を示す配管系統図、第
2図は本発明の一実施例の原子炉機器冷却系を示す配管
系統図、第3図は第2図に配設される各種弁の開閉を制
御する制御装置を示すブロック図、第4図は監視装置の
海水ループ監視ロジックを示すロジック図、第5図は監
視装置の中間ループ監視ロジックを示すロジック図であ
る。 1・・・・・・・・・・・・残留熱除去熱交換器2・・
・・・・・・・・・・原子炉−次冷11水ループ3・・
・・・・・・・・・・中間ループ4a 、4b・・・中
間ループ熱交換器5・・・・・・・・・・・・尚水ルー
プ6a 、6b・・・海水取込口 ア・・・・・・・・・・・・内水放出口8a 、8b・
・・海水ポンプ
Fig. 1 is a piping system diagram showing a conventional reactor equipment cooling system, Fig. 2 is a piping system diagram showing a reactor equipment cooling system according to an embodiment of the present invention, and Fig. 3 is a piping system diagram showing a reactor equipment cooling system according to an embodiment of the present invention. FIG. 4 is a logic diagram showing the seawater loop monitoring logic of the monitoring device, and FIG. 5 is a logic diagram showing the intermediate loop monitoring logic of the monitoring device. 1... Residual heat removal heat exchanger 2...
・・・・・・・・・Reactor-subcooling 11 water loop 3・・
...... Intermediate loop 4a, 4b... Intermediate loop heat exchanger 5...... Water loop 6a, 6b... Seawater intake a・・・・・・・・・Inland water outlet 8a, 8b・
・・Seawater pump

Claims (1)

【特許請求の範囲】[Claims] 湧水ポンプにより吸引された海水を中間ループ熱交換器
の低温側に循環させる海水ルー1と、前記中間ループ熱
交換器の高温側と残留熱除去熱交換器の低温側との間に
中間ループ循環ポンプにより冷fil水を循環させる中
間ループと、前記海水ポンプで吸引された海水を前記海
水ボンノまたは中間ループ循環ポンプのいずれか一方を
介して前記残留熱除去熱交換器の低温側に流入させる開
閉弁の介挿される吸込バイパスラインと、前記残留熱除
去熱交換器の低温側に流入した前記海水を海水放出口か
ら高水中に放出する放出バイパスラインとからなること
を特徴とする原子炉機器冷却系。
A seawater loop 1 circulates the seawater sucked by the spring water pump to the low temperature side of the intermediate loop heat exchanger, and an intermediate loop is provided between the high temperature side of the intermediate loop heat exchanger and the low temperature side of the residual heat removal heat exchanger. an intermediate loop in which cold filtration water is circulated by a circulation pump, and seawater sucked in by the seawater pump is caused to flow into the low temperature side of the residual heat removal heat exchanger through either the seawater bonno or the intermediate loop circulation pump. Nuclear reactor equipment comprising a suction bypass line into which an on-off valve is inserted, and a discharge bypass line that discharges the seawater that has flowed into the low temperature side of the residual heat removal heat exchanger into high water from a seawater discharge port. cooling system.
JP57125362A 1982-07-19 1982-07-19 Cooling circuit for reactor equipment Pending JPS5915891A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57125362A JPS5915891A (en) 1982-07-19 1982-07-19 Cooling circuit for reactor equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57125362A JPS5915891A (en) 1982-07-19 1982-07-19 Cooling circuit for reactor equipment

Publications (1)

Publication Number Publication Date
JPS5915891A true JPS5915891A (en) 1984-01-26

Family

ID=14908252

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57125362A Pending JPS5915891A (en) 1982-07-19 1982-07-19 Cooling circuit for reactor equipment

Country Status (1)

Country Link
JP (1) JPS5915891A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2574299A (en) * 2018-03-30 2019-12-04 Hitachi Ge Nuclear Energy Ltd Sea water cooling system

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2574299A (en) * 2018-03-30 2019-12-04 Hitachi Ge Nuclear Energy Ltd Sea water cooling system
GB2574299B (en) * 2018-03-30 2020-05-27 Hitachi Ge Nuclear Energy Ltd Sea water cooling system
GB2580573A (en) * 2018-03-30 2020-07-22 Hitachi Ge Nuclear Energy Ltd Sea Water Cooling System
GB2580573B (en) * 2018-03-30 2021-01-13 Hitachi Ge Nuclear Energy Ltd Sea Water Cooling System

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