JPS5882193A - Device for cleaning residual heat removal pipeline - Google Patents

Device for cleaning residual heat removal pipeline

Info

Publication number
JPS5882193A
JPS5882193A JP56179718A JP17971881A JPS5882193A JP S5882193 A JPS5882193 A JP S5882193A JP 56179718 A JP56179718 A JP 56179718A JP 17971881 A JP17971881 A JP 17971881A JP S5882193 A JPS5882193 A JP S5882193A
Authority
JP
Japan
Prior art keywords
residual heat
heat removal
water
cleaning
piping system
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
JP56179718A
Other languages
Japanese (ja)
Inventor
小玉 郁夫
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP56179718A priority Critical patent/JPS5882193A/en
Publication of JPS5882193A publication Critical patent/JPS5882193A/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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Cleaning In General (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】 本発明は1通常停止系の配管系の洗浄に係り。[Detailed description of the invention] The present invention relates to cleaning of a piping system in a normally stopped system.

特に定期的に洗浄廃液を発生し、その処理を他の処理系
で行なう必要がある原子カプラントの残留熱除去系に好
適な配管系洗浄に関する。
In particular, the present invention relates to piping system cleaning suitable for a residual heat removal system of an atomic couplant, which periodically generates cleaning waste liquid, which must be treated in another treatment system.

BWRプラントの残留熱除去系は、非常用炉心冷却と停
止時残留熱除去の機能を有し、プラント通常運転中には
、万一の事故に備え、非常用炉心冷却機能が果せるよう
配管系は充水しである。プラント停止時には原子炉−次
系と閉ループを構成して原子炉を冷却するが、この運転
に先立ち、配管系の洗浄を行ない、原子炉へ不純物を持
ち込むことを最小限にする。
The residual heat removal system of a BWR plant has the functions of emergency core cooling and residual heat removal during shutdown, and during normal plant operation, the piping system is designed to perform the emergency core cooling function in case of an accident. It is full of water. When the plant is shut down, a closed loop is formed with the reactor-subsystem to cool the reactor, but prior to operation, the piping system is cleaned to minimize the introduction of impurities into the reactor.

従来の配管系洗浄は復水脱塩水を他系統から導き置換す
る方法となっていたので、配管系の保有水をドレンした
後、復水脱塩水を満水する操作を数回繰返すか、給・排
水を同時に行ない稀釈する操作を行なうため、 (イ)他給水(復水脱塩水)を必要とする。
Conventional piping system cleaning has been carried out by introducing condensate demineralized water from another system and replacing it. Therefore, after draining the piping system of water, the operation of filling it with condensate demineralized water is repeated several times, or the supply and Since drainage and dilution are performed at the same time, (a) another water supply (condensate desalinated water) is required.

(ロ)配管系保有水の数倍の復水脱塩水を消費する。(b) Consuming condensed desalinated water several times as much as the water held in the piping system.

(ハ)排水は廃棄物処理系で処理後再利用に供されるが
、廃棄物処理系の処理量が増大する。
(c) Although wastewater is treated and reused in a waste treatment system, the amount of waste water to be processed by the waste treatment system increases.

という欠点があった。There was a drawback.

本発明の目的は、残留熱除去配管系の洗浄に際し、他給
水を不要にすると共に、配管系洗浄排水を発生させない
方法を提供することにある。
An object of the present invention is to provide a method that eliminates the need for additional water supply and does not generate drainage water for cleaning the piping system when cleaning the residual heat removal piping system.

配管系の洗浄を復水脱塩水と置換することで行なってい
るため、他給水を必要とし、洗浄排水が発生する。これ
らを解決するためには、残留熱除去配管系の保有水を、
ろ過脱塩装置を含む閉ループ内で循環浄化することで対
処できる。
Because the piping system is cleaned by replacing it with condensed demineralized water, other water supplies are required and cleaning wastewater is generated. In order to solve these problems, the water retained in the residual heat removal piping system must be
This can be dealt with by circulating purification in a closed loop that includes a filtration and desalination device.

以下、本発明の一実施例を第1図により説明する。原子
炉停止時の残留熱除去系の運転は、原子炉圧力容器1か
ら格納容器3を貫通する配管に設けられた隔離弁4およ
び5を通じ、残留熱除去ポンプ7で冷却材を取り出して
残留熱除去熱交換器8で冷却し、再び格納容器3を貫通
する配管に設けられた隔離弁9全通して原子炉圧力容器
1へ戻す閉ループで行なう。この運転に先立って、隔離
弁5.残留熱除去ポンプ7、残留熱除去熱交換器8、隔
離弁9の配管系を洗浄する。
An embodiment of the present invention will be described below with reference to FIG. The residual heat removal system operates when the reactor is shut down by extracting coolant from the residual heat removal pump 7 through isolation valves 4 and 5 installed in the piping that passes from the reactor pressure vessel 1 to the containment vessel 3. The process is performed in a closed loop in which the water is cooled in the removal heat exchanger 8 and returned to the reactor pressure vessel 1 through the entire isolation valve 9 provided in the piping that penetrates the containment vessel 3. Prior to this operation, the isolation valve 5. The piping system of the residual heat removal pump 7, residual heat removal heat exchanger 8, and isolation valve 9 is cleaned.

ここでは、BWRプラントの燃料プール冷却浄化系のろ
過脱塩装置13を残留熱除去配管系洗浄に流用する例に
ついて示す。
Here, an example will be shown in which the filtration desalination device 13 of the fuel pool cooling and purification system of a BWR plant is used for residual heat removal piping system cleaning.

燃料プール冷却浄化系は、使用済燃料貯蔵プール10、
スキマサージタンク11、燃料プール冷却浄化ポンプ1
2.ろ過脱塩装置13.燃料プール冷却熱交換器14、
散水管15から構成され、ろ過脱塩装・置13で使用済
燃料貯蔵プール水を浄化し、燃料プール冷却熱交換器1
4で使用済燃料の崩壊熱を除去する。使用済燃料貯蔵プ
ール10に使用済燃料がある場合は、燃料プール冷却浄
化系はプール水の常時浄化・冷却運転を行っているが、
原子炉停止時に残留熱除去配管系の洗浄に一時期ろ過脱
塩装置13を切離しても、使用済燃料貯蔵プールの冷却
水の冷却機能が維持されていれば何ら問題ない。従って
、残留熱除去配管系の洗浄時には、ろ過脱塩装置13の
入口弁16.出口弁17を閉め、バイパス弁18を開け
ることによって、燃料プール冷却浄化系の冷却機能を損
なわずに、ろ過脱塩装置13を残留熱除去配管系の洗浄
に供すことができる。残留熱除去配管系の洗浄時の状態
を第2図に、洗浄完了後の残留熱除去系の運転状態を第
3図に示す。本実施例によれば残留熱除去配管系の洗浄
に、他給水を必要とせず配管系洗浄排水を発生させない
効果がある。
The fuel pool cooling and purification system includes a spent fuel storage pool 10,
Skimmer surge tank 11, fuel pool cooling purification pump 1
2. Filtration desalination equipment 13. fuel pool cooling heat exchanger 14;
It is composed of a water sprinkler pipe 15, which purifies the spent fuel storage pool water with a filtration and desalination device/device 13, and a fuel pool cooling heat exchanger 1.
Step 4 removes the decay heat of the spent fuel. When there is spent fuel in the spent fuel storage pool 10, the fuel pool cooling and purification system constantly purifies and cools the pool water.
Even if the filtration and demineralization device 13 is temporarily disconnected to clean the residual heat removal piping system when the reactor is shut down, there is no problem as long as the cooling function of the cooling water in the spent fuel storage pool is maintained. Therefore, when cleaning the residual heat removal piping system, the inlet valve 16. By closing the outlet valve 17 and opening the bypass valve 18, the filtration and demineralization device 13 can be used for cleaning the residual heat removal piping system without impairing the cooling function of the fuel pool cooling and purification system. FIG. 2 shows the state of the residual heat removal piping system during cleaning, and FIG. 3 shows the operating state of the residual heat removal system after cleaning is completed. According to this embodiment, there is an effect that no other water supply is required for cleaning the residual heat removal piping system, and no piping system cleaning wastewater is generated.

燃料プール冷却浄化系のろ過脱塩装置13以外のろ過脱
塩装着を用いる場合、残留熱除去配管系の保有水を循環
浄化させるためは残留熱除去ポンプ以外のポンプを用い
る場合も同じ効果が得られる。
When using a filtration desalination device other than the filtration desalination device 13 in the fuel pool cooling and purification system, the same effect can be obtained when using a pump other than the residual heat removal pump to circulate and purify the water held in the residual heat removal piping system. It will be done.

本発明によれば、残留熱除去配管系の保有水を系外に排
出せず閉サイクル運転で配管系を洗浄できるので。
According to the present invention, the piping system can be cleaned in a closed cycle operation without discharging the water retained in the residual heat removal piping system to the outside of the system.

(イ)他給水(復水脱塩水)を必要としない。(a) No other water supply (condensed desalinated water) is required.

(ロ)通常年1回の定検停止に標し、洗浄排水的200
m”を発生しなくなる。
(b) 200 yen for cleaning waste water, aiming at regular inspection stoppage which is usually done once a year.
m” will no longer occur.

(ハ)原子炉停止時に廃棄物処理系の処理負荷を約20
0m3軽減できる。
(c) Reduce the processing load of the waste treatment system by approximately 20% when the reactor is shut down.
0m3 can be reduced.

(ニ)配管系内の保有水を、復水脱塩水に稀釈置換する
方法に対し、保有水のみを循環浄化するので配管系の洗
浄に要する時間を短縮できる。
(d) Compared to the method of diluting and replacing the retained water in the piping system with condensed demineralized water, only the retained water is circulated and purified, so the time required for cleaning the piping system can be shortened.

等の効果がある。There are other effects.

【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系統図、第2図は第1
図による残留熱除去配管系の洗浄運転を示す系統図、第
3図は洗浄運転終了後の残留熱除去系の運転を示す系統
図である。 1・・・原子炉圧力容器、2・・・冷却材再循環ポンプ
Fig. 1 is a system diagram showing one embodiment of the present invention, and Fig. 2 is a system diagram showing an embodiment of the present invention.
FIG. 3 is a system diagram showing the cleaning operation of the residual heat removal piping system. FIG. 3 is a system diagram showing the operation of the residual heat removal system after the cleaning operation is completed. 1...Reactor pressure vessel, 2...Coolant recirculation pump.

Claims (1)

【特許請求の範囲】[Claims] 1、原子炉容器内の冷却材の残留熱を除去する系統の配
管と燃料貯蔵プールの冷却材浄化系の脱塩器を管路にて
連絡し、残留熱除去系の配管内の冷却材浄化と燃料貯蔵
プールの冷却材浄化を切換える手段を有する残留熱除去
系配管の浄化装置。
1. Connect the piping of the system that removes the residual heat of the coolant in the reactor vessel with the demineralizer of the coolant purification system of the fuel storage pool, and purify the coolant in the piping of the residual heat removal system. and a residual heat removal system piping purification device having means for switching the coolant purification of the fuel storage pool.
JP56179718A 1981-11-11 1981-11-11 Device for cleaning residual heat removal pipeline Pending JPS5882193A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56179718A JPS5882193A (en) 1981-11-11 1981-11-11 Device for cleaning residual heat removal pipeline

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56179718A JPS5882193A (en) 1981-11-11 1981-11-11 Device for cleaning residual heat removal pipeline

Publications (1)

Publication Number Publication Date
JPS5882193A true JPS5882193A (en) 1983-05-17

Family

ID=16070652

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56179718A Pending JPS5882193A (en) 1981-11-11 1981-11-11 Device for cleaning residual heat removal pipeline

Country Status (1)

Country Link
JP (1) JPS5882193A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61133900A (en) * 1984-12-04 1986-06-21 株式会社日立製作所 Method and device for purifying nuclear reactor coolant

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61133900A (en) * 1984-12-04 1986-06-21 株式会社日立製作所 Method and device for purifying nuclear reactor coolant

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