JPS58162895A - Strainer cleaning device of emergency core cooling device - Google Patents
Strainer cleaning device of emergency core cooling deviceInfo
- Publication number
- JPS58162895A JPS58162895A JP57044566A JP4456682A JPS58162895A JP S58162895 A JPS58162895 A JP S58162895A JP 57044566 A JP57044566 A JP 57044566A JP 4456682 A JP4456682 A JP 4456682A JP S58162895 A JPS58162895 A JP S58162895A
- Authority
- JP
- Japan
- Prior art keywords
- strainer
- water
- core cooling
- emergency core
- test
- 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
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Casting Devices For Molds (AREA)
- Moulds For Moulding Plastics Or The Like (AREA)
- Transformer Cooling (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】
本発明は洗浄機能テストの自動化を可能とじ九特に沸騰
水型原子炉における非常炉心冷却装置のストレーナ洗浄
装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a strainer cleaning device for an emergency core cooling system in a boiling water nuclear reactor, which enables automation of cleaning function tests.
従来、沸騰水型原子炉の非常炉心冷却装置の注水装置と
して、例えば第1図に示すようなものがある。即ち、原
子炉1の冷却材喪失事故の際、原子炉格納容器2内の圧
力抑制室3に蓄えられている圧力抑制室プール水4を原
子炉に補給するようにしたものである。プール水4は、
ストレーナ5によって水中に含まれる異物を除去した後
、ポンプ吸込弁6を経て注入ポンプ7によって昇圧され
、しかる後注入配管8を介して原子炉へ注入されるもの
である。BACKGROUND ART Conventionally, as a water injection device for an emergency core cooling system of a boiling water reactor, there is one shown in FIG. 1, for example. That is, in the event of a loss of coolant accident in the reactor 1, the pressure suppression chamber pool water 4 stored in the pressure suppression chamber 3 in the reactor containment vessel 2 is supplied to the reactor. Pool water 4 is
After foreign matter contained in the water is removed by a strainer 5, the pressure is increased by an injection pump 7 through a pump suction valve 6, and then the water is injected into the nuclear reactor via an injection pipe 8.
ところで、この注水装置では、注水機能の健全性確認の
ため、定期的な機能テストが必要とされる。例えば数ケ
月毎に実施するのが一般的である。By the way, this water injection device requires periodic functional tests to confirm the soundness of the water injection function. For example, it is common to perform this every few months.
この機能テストは、注入配管8かも分岐するテスト配管
9を用いて圧力抑制室3のプール水を、ストレーナ5、
ポンプ吸込弁6、注入ポンプ7、テスト弁10からなる
循環経路を循環させることによって行なう。In this function test, the pool water in the pressure suppression chamber 3 is transferred to the strainer 5, using the test pipe 9 which also branches from the injection pipe 8.
This is carried out by circulating a circulation path consisting of a pump suction valve 6, an injection pump 7, and a test valve 10.
かるに、従来ではプール水に異物が混入し、機能テスト
の実施によジストレーナ5が経年的に目詰シし、該スト
レーナ部の圧力損失が増大する場合がおる。この圧力損
失が許容値以上になると注入ポンプ7の有効正味吸込水
頭が必要正味吸込水頭を上回り、注入ポンプにキャビテ
ーションが発生して、注水装置としての必要なポンプ流
量が確保できなくなる不都合が生じる。そこで、かかる
不都合を解消するため、ストレーナの圧力損失が許容値
に至った場合にこれを洗浄することが必要であるが、こ
のストレーナは、圧力抑制室3に設置されているため、
この圧力抑制室3からプール水を抜かなければならない
。However, in the conventional method, foreign matter may be mixed into the pool water, and the strainer 5 may become clogged over time during a functional test, resulting in an increase in pressure loss in the strainer portion. When this pressure loss exceeds the allowable value, the effective net suction head of the injection pump 7 exceeds the required net suction head, cavitation occurs in the injection pump, and the necessary pump flow rate for the water injection device cannot be secured. Therefore, in order to eliminate this inconvenience, it is necessary to clean the strainer when the pressure loss reaches an allowable value, but since this strainer is installed in the pressure suppression chamber 3,
Pool water must be drained from this pressure suppression chamber 3.
ところが、圧力抑制室3内のプール水には放射性物質が
含まれているため、この水抜き専用の貯留槽を設けると
か、流体放射性廃棄物の処理などが必要となる問題が生
じる。However, since the pool water in the pressure suppression chamber 3 contains radioactive substances, problems arise, such as the need to provide a storage tank exclusively for draining this water, and the need to dispose of fluid radioactive waste.
なお、第2図は圧力抑制室内のストレーナ目詰シ率と圧
力損失との関係の一例を示している。目詰シ率の増加に
伴なって圧力損失が曲線CIの如く増加する。例えば目
詰シ率が50%で圧力損失の許容値C2を超過するので
、このCt超過以前にストレーナの洗浄が必要となるこ
とが判る。Note that FIG. 2 shows an example of the relationship between the strainer clogging rate and pressure loss in the pressure suppression chamber. As the clogging rate increases, the pressure loss increases as shown by curve CI. For example, since a clogging rate of 50% exceeds the allowable pressure loss value C2, it is understood that the strainer needs to be cleaned before this Ct is exceeded.
本発明は以上の事情に基づいてなされ九もので、ストレ
ーナの洗浄を、圧力抑制室のプール水を抜く必要なく、
従って外部から洗浄水供給の必要もなく、機能テストを
自動的に行なえる非常炉心冷却装置のストレーナ洗浄装
置を提供することを目的とする。The present invention has been made based on the above circumstances, and allows cleaning of the strainer without the need to drain the pool water from the pressure suppression chamber.
Therefore, it is an object of the present invention to provide a strainer cleaning device for an emergency core cooling system that can automatically perform a functional test without the need to supply cleaning water from the outside.
かかる目的は、注水配管を機能テストする機能テスト配
管の吐出先端を異なる注水装置のストレーナに逆流可能
に接続し、この循環経路による内部逆流によってストレ
ーナを自動的に洗浄可能と7 した本発明によって達成
される。This object has been achieved by the present invention, in which the discharge tip of a function test pipe for functionally testing a water injection pipe is connected to a strainer of a different water injection device so that the flow can flow back, and the strainer can be automatically cleaned by the internal backflow through this circulation path. be done.
以下、本発明の一実施例を第3図を参照して説明する。An embodiment of the present invention will be described below with reference to FIG.
なお、第1図と共通部分には同一符号を用いる。Note that the same reference numerals are used for parts common to those in FIG.
一つのテスト配管9を、異なる注入配管18に設置・た
注入ポンプ17の吸込側に接続している。One test pipe 9 is connected to the suction side of an injection pump 17 installed in a different injection pipe 18.
即ち、圧力抑制室3の外側で、ポンプ吸込弁16の上流
側に接続している。そして、各注水装置の機能テストを
行なう場合は、自系統装置のテスト弁10を開とし、他
系統装置のポンプ吸込弁16を閉として、注入ポンプ7
を運転するものである。That is, it is connected to the upstream side of the pump suction valve 16 on the outside of the pressure suppression chamber 3 . When performing a function test of each water injection device, the test valve 10 of the own system device is opened, the pump suction valve 16 of the other system device is closed, and the injection pump 7
It is for driving.
秀即ち、この場合のテスト循環経路は、圧力抑制室内の
ストレーナ5、ポンプ吸込弁6、注入ポンプ7、テスト
配管9、テスト弁101異なるストレーナ15及び圧力
抑制室3によって構成される。That is, the test circulation path in this case is constituted by the strainer 5 in the pressure suppression chamber, the pump suction valve 6, the injection pump 7, the test pipe 9, the test valve 101, a different strainer 15, and the pressure suppression chamber 3.
なお、19.20は異なるテスト配管、テスト弁を夫々
示すう
このような循項路構成であると、ストレーナ15が通常
と逆向きの流れとなるため、このストレーナ15部に付
着した異物は、この逆向きの流れによって除去されるも
のである。Note that 19.20 indicates different test pipes and test valves, respectively. If the circulation path is configured like this, the flow in the strainer 15 will be in the opposite direction to the normal flow, so foreign matter attached to the strainer 15 will be removed. It is removed by this flow in the opposite direction.
したがって、注水装置の機能テストによってストレーナ
15の洗浄テストが自動的に行なえるので、例えば数ケ
月毎に実施される機能テストによってストレーナ15の
経年的な目詰シが防止できるのは勿論であるが、ストレ
ーナ15の洗浄作用を、圧力抑制室3のプール水の循環
のみによって行なうようにし九ので、外部から特別に洗
浄水を供給する必要がない。よって洗浄中にも圧力抑制
室3のプール水の水位が上昇するおそれもない。Therefore, since the cleaning test of the strainer 15 can be automatically performed by the function test of the water injection device, it goes without saying that clogging of the strainer 15 over time can be prevented by the function test carried out every few months, for example. Since the cleaning action of the strainer 15 is performed only by circulating the pool water in the pressure suppression chamber 3, there is no need to specially supply cleaning water from the outside. Therefore, there is no fear that the water level of the pool water in the pressure suppression chamber 3 will rise even during cleaning.
なお、テスト配管を、原子炉格納容器を貫通しない構成
とすれば、これによシ原子炉格納容器の貫通部数量の低
減も図れる。Note that if the test piping is configured so that it does not penetrate the reactor containment vessel, it is possible to reduce the number of parts that penetrate the reactor containment vessel.
以上のように、本発明によれば、非常炉心冷却装置の注
水装置の機能テストの際、圧力抑制室内ストレーナの洗
浄が自動的に、かつ外部からの洗浄水供給の必要もな〈
実施できるようになり、水抜き専用の貯水槽を設けるこ
とを省略できると共に、流体放射性廃棄物の処理等の面
倒な作業の省略も図れ、所期の目的が達成できるもので
ある。As described above, according to the present invention, during a functional test of the water injection device of the emergency core cooling system, the pressure suppression chamber strainer can be cleaned automatically and there is no need to supply cleaning water from the outside.
This makes it possible to eliminate the need for a dedicated water storage tank for draining water, as well as eliminate troublesome work such as processing of fluid radioactive waste, thereby achieving the intended purpose.
第1図は従来例を示す配管構成図、第2図は目詰り状況
を示す特性図、第3図は本発明の一実施例を示す配管構
成図である。FIG. 1 is a piping configuration diagram showing a conventional example, FIG. 2 is a characteristic diagram showing a clogging situation, and FIG. 3 is a piping configuration diagram showing an embodiment of the present invention.
Claims (1)
管から原子炉に供給するようにした沸騰水型原子炉の非
常炉心冷却装置において、前記注水配管を機能テストす
る機能テスト配管の吐出先端を異なる注水装置のストレ
ーナに逆流惹起可能に接続し、この循環経路による内部
逆流によって前記ストレーナを自動的に洗浄可能とした
ことを特徴とする非常炉心冷却装置のストレーナ洗浄装
置。1. In an emergency core cooling system for a boiling water reactor in which pool water from a pressure suppression chamber is supplied to the reactor from an injection pipe through a strainer, water is injected into different discharge tips of the functional test pipes for functionally testing the water injection pipe. A strainer cleaning device for an emergency core cooling system, characterized in that the strainer is connected to a strainer of the device so as to cause backflow, and the strainer can be automatically cleaned by internal backflow caused by the circulation path.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57044566A JPS58162895A (en) | 1982-03-23 | 1982-03-23 | Strainer cleaning device of emergency core cooling device |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57044566A JPS58162895A (en) | 1982-03-23 | 1982-03-23 | Strainer cleaning device of emergency core cooling device |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS58162895A true JPS58162895A (en) | 1983-09-27 |
Family
ID=12695042
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP57044566A Pending JPS58162895A (en) | 1982-03-23 | 1982-03-23 | Strainer cleaning device of emergency core cooling device |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS58162895A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2017090187A (en) * | 2015-11-09 | 2017-05-25 | 株式会社東芝 | Nuclear reactor water injection system and device for strainer cleaning |
-
1982
- 1982-03-23 JP JP57044566A patent/JPS58162895A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2017090187A (en) * | 2015-11-09 | 2017-05-25 | 株式会社東芝 | Nuclear reactor water injection system and device for strainer cleaning |
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