JPS5836320B2 - Genshironiokel - Google Patents
GenshironiokelInfo
- Publication number
- JPS5836320B2 JPS5836320B2 JP49062832A JP6283274A JPS5836320B2 JP S5836320 B2 JPS5836320 B2 JP S5836320B2 JP 49062832 A JP49062832 A JP 49062832A JP 6283274 A JP6283274 A JP 6283274A JP S5836320 B2 JPS5836320 B2 JP S5836320B2
- Authority
- JP
- Japan
- Prior art keywords
- housing
- cooling water
- primary cooling
- purified
- water 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.)
- Expired
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
-
- 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
- Cleaning In General (AREA)
Description
【発明の詳細な説明】
本発明は原子炉の制御棒駆動装置、中性子監視装置の収
容ハウジング内の堆積放射化スラツジの除去方法に関す
るものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for removing accumulated activation sludge in a housing for a control rod drive device and a neutron monitoring device of a nuclear reactor.
原子炉においては1次冷却水を循環ポンプにより炉内を
循環させ、その際発生する蒸気をタービンに送って発電
するものである。In a nuclear reactor, primary cooling water is circulated within the reactor by a circulation pump, and the steam generated at this time is sent to a turbine to generate electricity.
しかしこの1次冷却水中のスラツジを完全になくすこと
は困難であるので、運転を継続すると放射能レベルの高
い放射化スラツジが炉内の水溜り部などに堆積する。However, it is difficult to completely eliminate the sludge in the primary cooling water, so if the operation continues, radioactive sludge with a high radioactivity level will accumulate in water pools in the reactor.
例えば原子炉においては炉心を有する圧力容器の底部に
設けたハウジング内に、制御棒駆動装置所謂CHDと中
性子監視装置所謂PRMを収容設置して出力の制御など
が行われるが、ハウジングが1次冷却水の停滞部を形或
するので、ハウジング内に1次冷却水中のスラツジ即ち
レベルの高い放射化スラツジが堆積する。For example, in a nuclear reactor, a control rod drive device called CHD and a neutron monitoring device called PRM are housed and installed in a housing provided at the bottom of a pressure vessel containing the reactor core to control output, etc., but the housing is used for primary cooling. As water stagnation is formed, sludge in the primary cooling water, ie, a high level of activated sludge, accumulates within the housing.
従って定期点検時などにおける原子炉の休止時、1次冷
却水の放射能レベルが低下したのちまでも、上記堆積ス
ラツジによる高いレベルの放射源が残るため、上記制御
棒駆動装置などの交換点検に当っては作業員の高度な被
爆防備を必要とし、また人体の被爆量の制限から長時間
の作業が困難である。Therefore, when the reactor is shut down during periodic inspections, even after the radioactivity level of the primary cooling water has decreased, a high level radiation source remains due to the accumulated sludge, so it is necessary to inspect and replace the control rod drive device etc. This requires advanced radiation protection for workers, and it is difficult to work for long periods of time due to limitations on the amount of radiation the human body can be exposed to.
従って制御棒駆動装置のように定期検査時10〜30本
の交換作業を必要とする場合極めて多くの時間を必要と
し、作業能率を上げることができない。Therefore, when 10 to 30 rods need to be replaced during periodic inspections, such as in the case of a control rod drive device, it takes an extremely long time, and work efficiency cannot be improved.
本発明は以上の点に鑑みてなされたもので、制御棒駆動
装置などの収容ハウジング内に堆積した除去しにくい放
射化スラツジの簡単迅速な除去方法を提供し、作業環境
における放射能レベルの急速な低下と、作業能率の向上
を図りうるようにしたものである。The present invention has been made in view of the above points, and provides a simple and quick method for removing hard-to-remove radioactive sludge accumulated in the housing of a control rod drive device, etc., and rapidly reduces the radioactivity level in the working environment. This is designed to reduce the amount of damage caused and improve work efficiency.
次に図面を用いて詳細に説明する。原子炉には前記した
ように炉内を循環冷却する1次冷却水系の外に、1次冷
却水の一部を抽出して浄化したのち炉内に再送する浄化
水系を有している。Next, a detailed explanation will be given using the drawings. In addition to the primary cooling water system that circulates and cools the inside of the reactor as described above, the nuclear reactor has a purified water system that extracts a portion of the primary cooling water, purifies it, and then retransmits it into the reactor.
本発明は原子炉の休止後における各部の点検作業の開始
前に、1次冷却水系の循環ポンプと浄化水系の再循環ポ
ンプを作動状態として、浄化水系により浄化された冷却
水の一部を収容ハウジングの底部側面に設けた注水孔か
ら、収容ハウジングと制御棒.駆動装置との間隙内に噴
射注水し、その強い水流により堆積スラツジを洗浄除去
して炉内を循環する1次冷却水中に戻して浄化水系に送
り込むことを特徴とする除去方法である。The present invention operates the circulation pump of the primary cooling water system and the recirculation pump of the purified water system before starting the inspection work of each part after the reactor is shut down, and stores a part of the cooling water purified by the purified water system. The housing housing and control rod can be accessed through the water injection hole provided on the bottom side of the housing. This removal method is characterized by injecting water into the gap between the sludge and the drive device, and using the strong water flow to wash and remove the accumulated sludge, return it to the primary cooling water circulating in the furnace, and send it to the purified water system.
第1図は制御棒駆動装置などの収容ハウジングの堆積ス
ラツジの除去に適用した本発明の一実施例系統図、第2
図a,bは本発明を実施するために改造された制御棒駆
動装置と、中性子監視装置の収容ハウジングの断面図で
ある。Fig. 1 is a system diagram of one embodiment of the present invention applied to the removal of accumulated sludge in a housing housing such as a control rod drive device;
Figures a and b are cross-sectional views of a control rod drive device modified to implement the present invention and a housing housing for a neutron monitoring device.
第1図において1は炉心、2は圧力容器、3は制御棒駆
動装置などの収容ハウジング、このハウジングは第2図
a,bのように下部に注水孔3aを設けた筒状体3bを
原子炉の圧力容器2の底部2aに貫通固定したもので、
その下部開口部から制御棒駆動装置4、或いは中性子監
視装置5を挿しこんだのち、例えば駆動装置などの下端
に設けた鍔部4a或いは5aを、筒状体3bの下端に設
けたフランジ部3cに水密を保って結合し、交換点検が
可能なように形或されている。In Fig. 1, 1 is a reactor core, 2 is a pressure vessel, and 3 is a housing for housing control rod drive devices, etc., and this housing has a cylindrical body 3b with a water injection hole 3a in its lower part as shown in Figs. 2a and b. It is fixed through the bottom part 2a of the pressure vessel 2 of the furnace.
After inserting the control rod drive device 4 or the neutron monitoring device 5 through the lower opening, for example, the flange portion 3c provided at the lower end of the cylindrical body 3b is attached to the flange portion 4a or 5a provided at the lower end of the drive device, etc. It is shaped so that it can be connected watertightly and can be replaced and inspected.
なおハウジングから制御棒駆動装置などを引抜いたとき
、圧力容器内の1次冷却水がハウジングを介して外部に
排出されないようにするため、ハウジングを形成する筒
状体3bの上部に駆動装置の引抜きと連動して働く図示
しない弁を設けて筒状体の上端開口部を引抜き時自動的
に閉塞するようにしている。In addition, in order to prevent the primary cooling water in the pressure vessel from being discharged to the outside through the housing when the control rod drive device, etc. is pulled out from the housing, the drive device is removed at the top of the cylindrical body 3b forming the housing. A valve (not shown) that operates in conjunction with the cylindrical body is provided to automatically close the upper end opening of the cylindrical body when the cylindrical body is pulled out.
第1図に戻って6は循環ポンプ、7は配管、8は弁、9
はドレン弁、10はその上部配管で、これらによって1
次冷却水系を形威して炉内を循環冷却し、その際発生す
る蒸気を圧力容器2の上部に設けた配管11により図示
しないタービンに導いて発電する。Returning to Figure 1, 6 is a circulation pump, 7 is piping, 8 is a valve, 9
1 is the drain valve, 10 is its upper pipe, and 1
Next, a cooling water system is used to circulate and cool the inside of the reactor, and the steam generated at this time is guided to a turbine (not shown) through a pipe 11 provided at the upper part of the pressure vessel 2 to generate electricity.
12は浄化器、13は再循環ポンプ、14は配管、15
は弁、16は洗浄弁、17はその配管、18はドレン弁
、19は浄化水供給弁で、これらで浄化水系を形或し、
圧力容器2の底部から1次冷却水の一部を抽出して浄化
したのち、浄化水供給弁19、給水弁20、給水用配管
21を介して圧力容器2内に再送する。12 is a purifier, 13 is a recirculation pump, 14 is piping, 15
is a valve, 16 is a cleaning valve, 17 is its piping, 18 is a drain valve, and 19 is a purified water supply valve, these form a purified water system,
After a portion of the primary cooling water is extracted from the bottom of the pressure vessel 2 and purified, it is re-sent into the pressure vessel 2 via the purified water supply valve 19, the water supply valve 20, and the water supply piping 21.
また浄化水の一部は洗浄弁16、配管17を介して上記
収容ノ\ウジング3の下部に設けた注水孔3aに接続さ
れる。A portion of the purified water is also connected to a water injection hole 3a provided at the lower part of the housing nozzle 3 via a cleaning valve 16 and a pipe 17.
なお22は給水調整弁である。Note that 22 is a water supply regulating valve.
そこで前記したように点検作業の開始前に循環ポンプ6
により1次冷却水を炉内に循環させ、また再循環ポンプ
13により1次冷却水の浄化を図るようにした状態にお
いて、弁19を適当に絞り16を開けば、浄化された1
次冷却水の一部は注水孔3aから収容ハウジング3内の
下部に噴射注水されて、第2図a,bに示す矢印のよう
に収容ハウジング3から炉内にある強い水流を生ずる。Therefore, as mentioned above, before starting the inspection work,
When the primary cooling water is circulated in the reactor and the recirculation pump 13 is used to purify the primary cooling water, if the valve 19 is appropriately throttled and the valve 16 is opened, the purified 1
A portion of the next cooling water is injected into the lower part of the accommodation housing 3 through the water injection hole 3a, creating a strong water flow from the accommodation housing 3 into the furnace as indicated by the arrows shown in FIGS. 2a and 2b.
このため収容ハウジング3内に溜ったスラツジは上記の
強い浄化水流により洗浄除去されて炉内を循環する1次
冷却水中に戻り、浄化水系により浄化される。Therefore, the sludge accumulated in the accommodation housing 3 is washed away by the above-mentioned strong purified water flow, returns to the primary cooling water circulating in the furnace, and is purified by the purified water system.
従ってこの作業を所要時間継続すれば、この周辺におけ
る放射能レベルを急速に低下でき、原子炉休止後迅速に
制御棒駆動装置などの交換点検作業を行うことができる
。Therefore, if this work is continued for the required time, the radioactivity level in this area can be rapidly reduced, and the replacement and inspection work of the control rod drive device etc. can be carried out quickly after the reactor is shut down.
即ち本発明によれば収容ハウジングに注入孔を設けるこ
と5、浄化水の分岐を行う配管、弁などの簡単な設備の
改変によって、作業員を危険な直接作業から回避させる
ことがでキ、シかも除去したスラツジも浄化水のフィル
タによって処理されるので、作業員の直接作業の場合の
ように別に処理する方法に比べて危険がなく処理が簡単
である。That is, according to the present invention, workers can be avoided from dangerous direct work by providing an injection hole in the accommodation housing5 and by modifying simple equipment such as piping and valves for branching purified water. Since the removed sludge is also treated by the purified water filter, it is less dangerous and easier to treat than a separate treatment method that involves direct work by workers.
以上本発明を一実施例について説明したが、浄化水とガ
ス例えば窒素ガスの2相流体を噴射注入し、除去を更に
迅速確実にすることもできる。Although the present invention has been described above with reference to one embodiment, it is also possible to inject a two-phase fluid of purified water and a gas such as nitrogen gas to ensure faster removal.
以上の説明から明らかなように、本発明によれば原子炉
の1次冷却水系における堆積放射化スラツジを簡単迅速
に除去し、点検時における作業環境を良くすることがで
きる犬なる効果が得られるもので、実用上の効果は大き
い。As is clear from the above explanation, according to the present invention, the activated sludge deposited in the primary cooling water system of a nuclear reactor can be easily and quickly removed, and the working environment during inspections can be improved. This has great practical effects.
第1図および第2図a,bは制御棒駆動装置と中性子監
視装置の収容ハウジング内のスラツジ除去における本発
明の一実施例系統図および本発明を実施するための収容
ハウジングの構造例図である。Figures 1 and 2a and 2b are a system diagram of an embodiment of the present invention for removing sludge in a housing housing for a control rod drive device and a neutron monitoring device, and a structural example diagram of a housing housing for carrying out the present invention. be.
Claims (1)
の循環ポンプと浄化水系の再循環ポンプを作動状態とし
て、浄化水系により浄化された1次冷却水の一部を、制
御棒駆動装置と中性子監視装置の収容ハウジング内にそ
の底部から噴射注入して1次冷却水系に流出させ、その
際洗浄除去された堆積スラツジを浄化水系によって浄化
することを特徴とする原子炉における堆積放射化スラツ
ジの除去方法。1 Before inspection work after reactor shutdown, the circulation pump of the primary cooling water system and the recirculation pump of the purified water system are activated, and a portion of the primary cooling water purified by the purified water system is transferred to the control rod drive device. Activated sludge deposited in a nuclear reactor is injected from the bottom into a housing housing of a neutron monitoring device and discharged into a primary cooling water system, and the deposited sludge washed and removed at that time is purified by a purified water system. Removal method.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP49062832A JPS5836320B2 (en) | 1974-06-05 | 1974-06-05 | Genshironiokel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP49062832A JPS5836320B2 (en) | 1974-06-05 | 1974-06-05 | Genshironiokel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS50154696A JPS50154696A (en) | 1975-12-12 |
| JPS5836320B2 true JPS5836320B2 (en) | 1983-08-08 |
Family
ID=13211676
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP49062832A Expired JPS5836320B2 (en) | 1974-06-05 | 1974-06-05 | Genshironiokel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5836320B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0231148A (en) * | 1988-07-20 | 1990-02-01 | Kobe Steel Ltd | Method for measuring biomass |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4322790Y1 (en) * | 1966-08-03 | 1968-09-25 |
-
1974
- 1974-06-05 JP JP49062832A patent/JPS5836320B2/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0231148A (en) * | 1988-07-20 | 1990-02-01 | Kobe Steel Ltd | Method for measuring biomass |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS50154696A (en) | 1975-12-12 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP7598837B2 (en) | Chemical decontamination method and chemical decontamination apparatus | |
| JP6129646B2 (en) | Method for carrying out fuel debris in boiling water nuclear power plant | |
| JP2017223524A (en) | Chemical decontamination system and chemical decontamination method of reactor pressure vessel | |
| JPS5836320B2 (en) | Genshironiokel | |
| US4043864A (en) | Nuclear power plant having a pressurized-water reactor | |
| US5517539A (en) | Method of decontaminating a PWR primary loop | |
| TWI825540B (en) | Chemical decontamination methods and chemical decontamination devices | |
| KR102482934B1 (en) | System decontamination facilities | |
| JP7094900B2 (en) | Decontamination method and decontamination equipment | |
| JPS5941155B2 (en) | Reactor shutdown cooling system | |
| US12198825B2 (en) | Chemical decontamination method | |
| CN109003685A (en) | Floating system is gone in a kind of PWR nuclear power plant spentnuclear fuel pond | |
| JP7411502B2 (en) | Chemical decontamination method for carbon steel parts of nuclear power plants | |
| RU2110860C1 (en) | Decontaminating process for multiple forced circulation loop of water-graphite reactors | |
| JP2575845B2 (en) | Temporary gap sealing structure and gap sealing method for nuclear reactor | |
| JP6776426B2 (en) | Decontamination method and decontamination equipment | |
| JPS59143996A (en) | Initial oxidation operation method for nuclear reactor plants | |
| JP2011099801A (en) | Reactor well cover and reactor inspection method | |
| JP2001083300A (en) | Liquid metal target cooling system | |
| JPS6138435B2 (en) | ||
| JP2001235594A (en) | Chemical decontamination method in reactor pressure vessel | |
| JPS60140197A (en) | Treatment method for primary system piping | |
| JPS6223840B2 (en) | ||
| JPS5991399A (en) | Outer surface cleaning device of nuclear fuel | |
| JPS6319596A (en) | Pressure-suppression chamber pool-water system of nuclear power plant |