JPS63157100A - Nuclear-reactor auxiliary cooling facility - Google Patents

Nuclear-reactor auxiliary cooling facility

Info

Publication number
JPS63157100A
JPS63157100A JP61305677A JP30567786A JPS63157100A JP S63157100 A JPS63157100 A JP S63157100A JP 61305677 A JP61305677 A JP 61305677A JP 30567786 A JP30567786 A JP 30567786A JP S63157100 A JPS63157100 A JP S63157100A
Authority
JP
Japan
Prior art keywords
cooling
water
heat exchanger
cooling water
reactor auxiliary
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.)
Granted
Application number
JP61305677A
Other languages
Japanese (ja)
Other versions
JPH0634085B2 (en
Inventor
純 花輪
石田 暢生
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 Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
Toshiba 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 Toshiba Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP61305677A priority Critical patent/JPH0634085B2/en
Publication of JPS63157100A publication Critical patent/JPS63157100A/en
Publication of JPH0634085B2 publication Critical patent/JPH0634085B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は原子力発電所の原子炉補機冷却設備に関する。[Detailed description of the invention] [Purpose of the invention] (Industrial application field) The present invention relates to a nuclear reactor auxiliary cooling equipment for a nuclear power plant.

(従来の技術) 原子力発電所においては通常運転中の各機器の冷却、非
常時における原子炉残留熱の除去および非常用開蓋の冷
却を目的として原子炉補機冷却設備が設けられている。
(Prior Art) Nuclear power plants are provided with reactor auxiliary equipment cooling equipment for the purpose of cooling various equipment during normal operation, removing reactor residual heat in an emergency, and cooling an emergency opening lid.

この原子炉補機冷却設備は第3図に示すように原子炉補
機冷却ポンプ2により冷却水を冷却負荷1へ供給し、冷
却負荷1を冷却水で除熱する構成となっている。冷却負
荷1を出た冷却水は冷却水戻り配管5及び冷却水人口弁
6を通って原子炉補機冷却熱交換器3に流入する。この
熱交換器3では海水ポンプ10より供給される海水によ
り冷却水の除熱が行われ、熱交換器3を出た冷却水は冷
却水出口弁7及び冷却水供給配管4を通り、再び冷W負
荷1へ導入される。
As shown in FIG. 3, this reactor auxiliary equipment cooling equipment is configured such that a reactor auxiliary equipment cooling pump 2 supplies cooling water to a cooling load 1, and heat is removed from the cooling load 1 with the cooling water. The cooling water leaving the cooling load 1 flows into the reactor auxiliary equipment cooling heat exchanger 3 through the cooling water return pipe 5 and the cooling water population valve 6. In this heat exchanger 3, heat is removed from the cooling water by the seawater supplied from the seawater pump 10, and the cooling water exiting the heat exchanger 3 passes through the cooling water outlet valve 7 and the cooling water supply pipe 4, and is cooled again. W is introduced into load 1.

また、原子炉補機冷却設備には冷却水の温度変化による
体積減少および弁グランド部等のシール部から漏洩する
冷却水を補給する目的でサージタンク12が設けられて
いる。このサージタンク12は第4図に示すように水位
が通常水位18となるように水位11mされており、シ
ール部からの漏洩等により水位が補給水開始水位19ま
で低下すると補給水供給ライン13より補給水が供給さ
れ、水位が補給水停止水位17まで上昇すると補給水の
供給が停止するようになっている。なお、補給水供給う
イン13からの補給水流量はサージタンク12のオバー
フロー14に接続されているドレンファンネル15の排
水容量を考慮して最大9m’/hr程度になるように調
整されている。そして、サージタンク12内の水位は機
器、配管等の破断を検知する目的で常時監視されており
、例えば水位が高水位16まで上昇した場合には原子炉
補機冷却熱交交換器3あるいは冷却負荷1側より冷却水
循環ライン側へ流体が流入したと判断し、警報等が発せ
られる。また、水位が低水位20まで低下した場合には
配管の破断等により冷却水が外部へ漏洩したと判断し、
警報等が発せられる。
Additionally, a surge tank 12 is provided in the reactor auxiliary equipment cooling equipment for the purpose of replenishing cooling water that decreases in volume due to changes in cooling water temperature and leaks from seals such as valve glands. As shown in Fig. 4, this surge tank 12 is kept at a water level of 11 m so that the normal water level is 18, and when the water level drops to the make-up water start level 19 due to leakage from the seal, etc., the make-up water supply line 13 is Make-up water is supplied, and when the water level rises to make-up water stop level 17, the supply of make-up water is stopped. Note that the flow rate of make-up water from the make-up water supply inlet 13 is adjusted to a maximum of about 9 m'/hr in consideration of the drainage capacity of the drain funnel 15 connected to the overflow 14 of the surge tank 12. The water level in the surge tank 12 is constantly monitored for the purpose of detecting breaks in equipment, piping, etc. For example, if the water level rises to a high water level 16, the water level in the surge tank 12 is constantly monitored. It is determined that fluid has flowed from the load 1 side to the cooling water circulation line side, and an alarm etc. is issued. In addition, if the water level drops to low water level 20, it is determined that the cooling water has leaked to the outside due to a break in the pipe, etc.
A warning etc. will be issued.

このような原子炉補機冷却設備にあっては1つの系統に
複数の原子炉補機冷却熱交換器3が設備されており、系
統の運転中でも原子炉補機冷却熱交換器3のメンテナン
スが実施できるようになっている。原子炉補機冷却熱交
換器3のメンテナンスを実施する場合は、まず冷却水入
口弁6.冷却水出口弁7.海水入口弁8および海水出口
弁9の器片を閏とし、熱交換器3内の水抜きを行った後
に分解及び点検を行う。
In such a reactor auxiliary cooling equipment, a plurality of reactor auxiliary cooling heat exchangers 3 are installed in one system, and maintenance of the reactor auxiliary cooling heat exchangers 3 is required even when the system is in operation. It is now possible to implement. When performing maintenance on the reactor auxiliary equipment cooling heat exchanger 3, first check the cooling water inlet valve 6. Cooling water outlet valve7. Disassemble and inspect the heat exchanger 3 after draining the water inside the heat exchanger 3 using the pieces of the seawater inlet valve 8 and seawater outlet valve 9 as screws.

また、メンテナンス後の熱交換器3の水張りを実施する
場合は、まずベンド弁11を開とし、開状態の冷却水入
口弁6を微開とした後、徐々に熱交換器3内に冷却水を
流入させて水張りを行う。
In addition, when filling the heat exchanger 3 with water after maintenance, first open the bend valve 11, then slightly open the open cooling water inlet valve 6, and then gradually fill the heat exchanger 3 with cooling water. Fill the area with water by letting it flow in.

この場合、熱交換器3内へ流入する冷却水流量をサージ
タンク12への補給水流量(9m3/hr)以下とする
必要があるが、冷却水人口弁6は比較的大口径(400
A程度)の仕切弁であることが多い。そのため、熱交換
器3への冷却水流量が9m”/hr以下となるように冷
却水人口弁6の弁開度を調整することは極めて難しく、
弁開度が必要以上に開状態となってしまい、熱交換器3
への冷却水流量がサージタンク12への補給水流量を越
えてしまう可能性がある。
In this case, the flow rate of cooling water flowing into the heat exchanger 3 needs to be lower than the flow rate of makeup water to the surge tank 12 (9 m3/hr), but the cooling water population valve 6 has a relatively large diameter (400 m3/hr) or less.
It is often a gate valve of grade A). Therefore, it is extremely difficult to adjust the valve opening degree of the cooling water valve 6 so that the flow rate of cooling water to the heat exchanger 3 is 9 m"/hr or less.
The valve opening becomes more open than necessary, and heat exchanger 3
There is a possibility that the flow rate of cooling water to the surge tank 12 may exceed the flow rate of make-up water to the surge tank 12.

このように原子炉補機冷却熱交換器3の水張りに際して
熱交換器3への冷却水流量がサージタンク12への補給
水流量を越えてしまうと、サージタンク12の水位を通
常水位18に保つことができなくなり、水位低下の警報
信号やポンプの停止信号が発せられる可能性がある。
In this way, when the reactor auxiliary equipment cooling heat exchanger 3 is filled with water, if the flow rate of cooling water to the heat exchanger 3 exceeds the flow rate of make-up water to the surge tank 12, the water level of the surge tank 12 is maintained at the normal water level 18. This may result in a low water level warning signal or a pump stop signal being issued.

(発明が解決しようとする問題点) 以上のように従来の原子炉補機冷却設備においては、原
子炉補機冷却熱交換器3の水張りを実施する場合にサー
ジタンク12の水位が通常水位18より大きく低下する
可能性があり、プラントの運転に影響を及ぼすおそれが
あった。
(Problems to be Solved by the Invention) As described above, in the conventional reactor auxiliary cooling equipment, when filling the reactor auxiliary cooling heat exchanger 3 with water, the water level of the surge tank 12 is set to 18 There was a possibility that the decrease would be even greater, which could affect the operation of the plant.

本発明はこのような問題点に着目してなされたもので、
その目的とするところは、サージタンクの水位を大きく
低下させることなく原子炉補機冷却熱交換器の水張りを
実施することができる原子炉補機冷却設備を提供するこ
とにある。
The present invention was made by focusing on these problems.
The purpose is to provide a reactor auxiliary equipment cooling facility that can fill a reactor auxiliary equipment cooling heat exchanger with water without significantly lowering the water level of the surge tank.

[発明の構成] (問題点を解決するための手段) 上記目的を達成するために本発明は、原子炉補機冷却熱
交換器の冷却水入口ラインに冷却水入口弁をバイパスす
るバイパス配管を設けるとともに、同バイパス配管に熱
交換器への冷却水流量がサージタンクへの補給水流量以
下となる開閉弁を設けたことを特徴とするものである。
[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention provides bypass piping that bypasses the cooling water inlet valve in the cooling water inlet line of the reactor auxiliary equipment cooling heat exchanger. In addition, the bypass piping is provided with an on-off valve so that the flow rate of cooling water to the heat exchanger is equal to or less than the flow rate of make-up water to the surge tank.

(作 用) 本発明では原子炉補機冷却熱交換器の水張りを実施する
場合に冷却水をバイパス配管を通して熱交換器内へ流入
させることにより、熱交換器への冷却水流量をサージタ
ンクへの補給水流量以下にすることができる。
(Function) In the present invention, when filling the reactor auxiliary equipment cooling heat exchanger with water, cooling water flows into the heat exchanger through bypass piping, thereby controlling the flow rate of cooling water to the heat exchanger to the surge tank. The make-up water flow rate can be less than or equal to

(実 施 例) 以下、図面を参照して本発明の実施例について説明する
。なお、従来と同一部分には同一符号を付し、その説明
を省略する。第1図は本発明の一実施例を示す原子炉補
機冷却設備の概略構成図で、この原子炉補機冷却設備の
原子炉補機冷却熱交換器3の冷却水入口側には冷却水人
口弁6をバイバスするバイパス配管22が設けられ、さ
らにバイパス配管22には小口径(25A程度)の開閉
弁23が設けられている。したがって、原子炉補機冷却
熱交換器3の水張りを実施する場合はベンド弁11およ
び開閉弁23を開とし、バイパス配管22を通じて熱交
換器3内に冷却水を流入させる。このとき、熱交換器3
内へ流入する冷却水流量は開閉弁23の絞り効果により
サージタンク12への補給水流Jl (9m3/hr)
以下となるため、サージタンク12の水位を通常水位1
8に保つことができる。
(Example) Hereinafter, an example of the present invention will be described with reference to the drawings. Note that parts that are the same as those in the prior art are given the same reference numerals, and their explanations will be omitted. FIG. 1 is a schematic configuration diagram of a nuclear reactor auxiliary cooling equipment showing an embodiment of the present invention. A bypass pipe 22 is provided to bypass the artificial valve 6, and the bypass pipe 22 is further provided with an on-off valve 23 having a small diameter (about 25A). Therefore, when filling the reactor auxiliary equipment cooling heat exchanger 3 with water, the bend valve 11 and the on-off valve 23 are opened to allow cooling water to flow into the heat exchanger 3 through the bypass pipe 22. At this time, heat exchanger 3
The flow rate of cooling water flowing into the surge tank 12 is reduced by the throttling effect of the on-off valve 23 (9 m3/hr).
The water level in the surge tank 12 is set to the normal water level 1.
It can be kept at 8.

上述したように本実施例では、原子炉補機冷却熱交換器
3の冷却水入口側に冷却水入口弁6をバイパスするバイ
パス配管22を設けるとともに、このバイパス配管22
に熱交換器3の冷却水流量がサージタンク12への補給
水流量以下となる小口径の開閉弁23を設けることによ
り、サージタンク12の水位を通常水位18に保つこと
ができるため、サージタンク12の水位を大きく低下さ
せることなく原子炉補機冷却熱交換器3の水張りを実施
することができる。
As described above, in this embodiment, the bypass piping 22 that bypasses the cooling water inlet valve 6 is provided on the cooling water inlet side of the reactor auxiliary equipment cooling heat exchanger 3, and this bypass piping 22
By providing a small-diameter opening/closing valve 23 in which the cooling water flow rate of the heat exchanger 3 is lower than the make-up water flow rate to the surge tank 12, the water level of the surge tank 12 can be maintained at the normal water level 18. The reactor auxiliary equipment cooling heat exchanger 3 can be filled with water without significantly lowering the water level of the reactor auxiliary equipment cooling heat exchanger 3.

なお、上記実施例では原子炉補機冷却熱交換器3の水張
りをバイパス配管22を通して行うようにしたが、第2
図に示すように原子炉補機冷却熱交換器3と冷却水人口
弁6との間の冷却水戻り配管5に外部補給ライン24を
接続し、外部補給ライン24から冷却水を熱交換器3内
に直接流入させるようにしてもよい。
In the above embodiment, the reactor auxiliary equipment cooling heat exchanger 3 was filled with water through the bypass pipe 22, but the second
As shown in the figure, an external supply line 24 is connected to the cooling water return pipe 5 between the reactor auxiliary equipment cooling heat exchanger 3 and the cooling water population valve 6, and the cooling water is supplied from the external supply line 24 to the heat exchanger 3. It may also be made to flow directly into the interior.

[発明の効果] 以上説明したように本発明によれば、サージタンクの水
位を大きく低下させることなく原子炉補機冷却熱交換器
の水張りを実施することができ、サージタンクの水位低
下による種々の弊害を防止することができる。
[Effects of the Invention] As explained above, according to the present invention, it is possible to fill the reactor auxiliary equipment cooling heat exchanger with water without significantly lowering the water level of the surge tank, and various problems caused by a drop in the water level of the surge tank can be carried out. It is possible to prevent the harmful effects of

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

第1図は本発明の一実施例を示す原子炉補機冷却設備の
概略構成図、第2図は本発明の他の実施例を示す原子炉
補機冷却設備の概略構成図、第3図は従来の原子炉補機
冷却設備の概略構成図、第4図はサージタンクの通常水
位を示す断面図である。 1・・・冷却負荷、2・・・原子炉補機冷却ポンプ、3
・・・原子炉補機冷却熱交換器、6・・・冷却水人口弁
、7・・・冷却水出口弁、12・・・サージタンク、2
2・・・バイパス配管、23・・・開閉弁。 出願人代理人 弁理士 鈴江武彦 第1図 第2図 第3図
Fig. 1 is a schematic diagram of a reactor auxiliary cooling equipment showing one embodiment of the present invention, Fig. 2 is a schematic diagram of a reactor auxiliary cooling equipment showing another embodiment of the invention, and Fig. 3 4 is a schematic configuration diagram of a conventional nuclear reactor auxiliary cooling equipment, and FIG. 4 is a sectional view showing the normal water level of a surge tank. 1... Cooling load, 2... Reactor auxiliary equipment cooling pump, 3
...Reactor auxiliary equipment cooling heat exchanger, 6...Cooling water population valve, 7...Cooling water outlet valve, 12...Surge tank, 2
2...Bypass piping, 23...Opening/closing valve. Applicant's agent Patent attorney Takehiko Suzue Figure 1 Figure 2 Figure 3

Claims (1)

【特許請求の範囲】[Claims] 冷却負荷へ冷却水を供給する原子炉補機冷却ポンプと、
前記冷却負荷からの戻り冷却水を海水冷却する原子炉補
機冷却熱交換器と、この熱交換器より流出する冷却水を
前記原子炉補機冷却ポンプおよび冷却負荷を経由して循
環させる冷却水循環ラインと、この冷却水循環ラインに
冷却水を補給するサージタンクと、このサージタンクに
補給水を供給する補給水供給ラインとを備えた原子炉補
機冷却設備において、前記熱交換器の冷却水入口ライン
に冷却水入口弁をバイパスするバイパス配管を設けると
ともに、同バイパス配管に熱交換器への冷却水流量がサ
ージタンクへの補給水流量以下となる開閉弁を設けたこ
とを特徴とする原子炉補機冷却設備。
A reactor auxiliary equipment cooling pump that supplies cooling water to the cooling load;
A reactor auxiliary equipment cooling heat exchanger that cools the return cooling water from the cooling load with sea water, and a cooling water circulation that circulates the cooling water flowing out from the heat exchanger via the reactor auxiliary equipment cooling pump and the cooling load. In the reactor auxiliary equipment cooling equipment, the cooling water inlet of the heat exchanger is equipped with a surge tank that supplies cooling water to the cooling water circulation line, and a makeup water supply line that supplies makeup water to the surge tank. A nuclear reactor characterized in that a bypass piping that bypasses a cooling water inlet valve is provided in the line, and an on-off valve is provided in the bypass piping so that the flow rate of cooling water to the heat exchanger is equal to or less than the flow rate of make-up water to the surge tank. Auxiliary cooling equipment.
JP61305677A 1986-12-22 1986-12-22 Reactor auxiliary equipment cooling equipment Expired - Lifetime JPH0634085B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61305677A JPH0634085B2 (en) 1986-12-22 1986-12-22 Reactor auxiliary equipment cooling equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61305677A JPH0634085B2 (en) 1986-12-22 1986-12-22 Reactor auxiliary equipment cooling equipment

Publications (2)

Publication Number Publication Date
JPS63157100A true JPS63157100A (en) 1988-06-30
JPH0634085B2 JPH0634085B2 (en) 1994-05-02

Family

ID=17948023

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61305677A Expired - Lifetime JPH0634085B2 (en) 1986-12-22 1986-12-22 Reactor auxiliary equipment cooling equipment

Country Status (1)

Country Link
JP (1) JPH0634085B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2007187543A (en) * 2006-01-13 2007-07-26 Toshiba Corp Residual heat removal system and its operation method

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2007187543A (en) * 2006-01-13 2007-07-26 Toshiba Corp Residual heat removal system and its operation method
JP4542992B2 (en) * 2006-01-13 2010-09-15 株式会社東芝 Residual heat removal system and operation method thereof

Also Published As

Publication number Publication date
JPH0634085B2 (en) 1994-05-02

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