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JPH087273B2 - Test / cleaning device and test / cleaning method for nuclear power plant piping - Google Patents
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JPH087273B2 - Test / cleaning device and test / cleaning method for nuclear power plant piping - Google Patents

Test / cleaning device and test / cleaning method for nuclear power plant piping

Info

Publication number
JPH087273B2
JPH087273B2 JP1304716A JP30471689A JPH087273B2 JP H087273 B2 JPH087273 B2 JP H087273B2 JP 1304716 A JP1304716 A JP 1304716A JP 30471689 A JP30471689 A JP 30471689A JP H087273 B2 JPH087273 B2 JP H087273B2
Authority
JP
Japan
Prior art keywords
pipe
main steam
water supply
piping
supply 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 - Lifetime
Application number
JP1304716A
Other languages
Japanese (ja)
Other versions
JPH03167497A (en
Inventor
金雄 後藤
俊昭 好永
洋一 山根
重士 佐藤
操 安藤
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 JP1304716A priority Critical patent/JPH087273B2/en
Publication of JPH03167497A publication Critical patent/JPH03167497A/en
Publication of JPH087273B2 publication Critical patent/JPH087273B2/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
    • Y02E30/30Nuclear fission reactors

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 [産業上の利用分野] 本発明は、原子力発電設備の配管の試験・洗浄装置お
よび試験・洗浄方法に係り、特に原子力発電設備の建設
時における主蒸気系配管と給水系配管の水圧試験および
洗浄作業の能率向上に好適な配管の試験・洗浄装置およ
び方法に関する。
Description: TECHNICAL FIELD The present invention relates to a test / cleaning apparatus and a test / cleaning method for piping of nuclear power generation equipment, and particularly to a main steam system piping and water supply at the time of construction of nuclear power generation equipment. The present invention relates to a pipe testing / cleaning apparatus and method suitable for improving the efficiency of a hydraulic test and cleaning of system piping.

[従来の技術] 以下、第3図および第4図を参照して原子炉圧力容器
側の主蒸気系配管と給水系配管における水圧試験と洗浄
作業の従来技術を説明する。
[Prior Art] With reference to FIGS. 3 and 4, a prior art of a water pressure test and a cleaning operation in a main steam system pipe and a water supply system pipe on the reactor pressure vessel side will be described below.

第3図において、原子炉格納容器9の周囲にはシール
ドウオール13が設置されている。この原子炉格納容器9
内には原子炉圧力容器8が格納されており、この原子炉
圧力容器8は原子炉圧力容器ペデスタル12によって支持
されている。前記原子炉圧力容器8内で発生した主蒸気
は、主蒸気系配管1,14から主蒸気系隔離弁4、主蒸気第
3隔離弁5を通じてタービン(図示省略)に導かれる。
このタービンに導かれた主蒸気は、復水器(図示省略)
により凝縮され、復水となる。この復水は、給水系配管
15,2から給水系隔離弁3を通じて原子炉圧力容器8内に
導かれる。そして、復水は再循環系配管10から再循環ポ
ンプ11を介して昇圧され、原子炉圧力容器8内を下方か
ら上方に向かい、再び主蒸気となって主蒸気系配管1に
導かれるようになっている。
In FIG. 3, a shield wall 13 is installed around the reactor containment vessel 9. This reactor containment vessel 9
A reactor pressure vessel 8 is housed therein, and the reactor pressure vessel 8 is supported by a reactor pressure vessel pedestal 12. The main steam generated in the reactor pressure vessel 8 is guided to the turbine (not shown) from the main steam system pipes 1 and 14 through the main steam system isolation valve 4 and the main steam third isolation valve 5.
The main steam introduced to this turbine is a condenser (not shown)
Are condensed by and become condensed water. This condensate is used for water supply piping
It is introduced into the reactor pressure vessel 8 from the water supply system isolation valve 3 from 15,2. Then, the condensate is pressurized from the recirculation system pipe 10 through the recirculation pump 11, goes from the lower side to the upper side in the reactor pressure vessel 8, and becomes the main steam again to be guided to the main steam system pipe 1. Has become.

次に、第4図を参照して主蒸気系配管1および給水系
配管2の水圧試験の従来技術を説明する。
Next, with reference to FIG. 4, a conventional technique of the water pressure test of the main steam system pipe 1 and the water supply system pipe 2 will be described.

原子力発電設備の建設工事で、原子炉圧力容器側の主
蒸気系配管1,14および給水系配管2,15の施工が進み、原
子炉圧力容器8のノズル付近まで完成した時点で、水圧
試験を行う。この水圧試験には、従来技術では規定圧力
に耐え得るように製造された閉止キャップ6を使用して
行う。この閉止キャップ6を主蒸気系配管1に4個、給
水系配管2に6個、合計10個取り付ける。
In the construction work of the nuclear power generation facility, construction of the main steam system pipes 1,14 and water supply system pipes 2,15 on the reactor pressure vessel side proceeded, and a water pressure test was conducted at the time when the nozzles of the reactor pressure vessel 8 were completed. To do. This water pressure test is performed using a closure cap 6 manufactured in the prior art to withstand a specified pressure. This closure cap 6 is attached to the main steam system pipe 1 by 4 pieces and the water supply system pipe 2 by 6 pieces, a total of 10 pieces.

給水系配管2は、この時点で水圧試験が可能となる
が、主蒸気系配管1は主蒸気系隔離弁4を止めるため、
特殊治具17を取り付けた後に水圧試験が可能となる。
The water supply system pipe 2 can be subjected to a water pressure test at this point, but the main steam system pipe 1 stops the main steam system isolation valve 4,
After attaching the special jig 17, a water pressure test becomes possible.

これらの準備が完成した後に、水圧試験を実施する。
水圧試験は、溶接検査耐圧試験および使用前耐圧試験か
らなる。この水圧試験の都度、日本電気協会電気技術規
定に規定されている最低使用温度の確認のため、配管の
温度を規定温度に上げなければならない。そのため、ハ
ウスボイラの蒸気を注入するが、循環方法を適切に行わ
ないと検査ができなくなる。
After these preparations are completed, a hydraulic test is carried out.
The water pressure test consists of a welding inspection pressure resistance test and a pre-use pressure resistance test. Every time this water pressure test is performed, the temperature of the piping must be raised to the specified temperature in order to confirm the minimum operating temperature specified in the Electrical Engineering Regulations of the Japan Electric Association. Therefore, the steam of the house boiler is injected, but the inspection cannot be performed unless the circulation method is properly performed.

このようにして水圧試験が終了すると、次のステップ
である配管の洗浄準備に取り掛かる。
When the water pressure test is completed in this way, the next step, which is the preparation for cleaning the pipe, is started.

すなわち、配管の洗浄は、水または水に薬品を溶かし
た溶液を配管内に注入し、従来技術では洗浄対象配管で
循環ループを作り、溶液を循環させて行う。この洗浄時
には、配管の圧力を考える必要はなく、洗浄ルートのみ
の仮配管をして洗浄を行っていた。
That is, the cleaning of the pipe is performed by injecting water or a solution in which a chemical is dissolved into the pipe, and in the related art, a circulation loop is formed in the pipe to be cleaned and the solution is circulated. At the time of this cleaning, it is not necessary to consider the pressure of the piping, and the temporary piping only for the cleaning route was used for cleaning.

[発明が解決しようとする課題] 前記従来技術により、水圧試験および洗浄作業を行う
場合には、次のような問題がある。
[Problems to be Solved by the Invention] When performing a hydraulic test and a cleaning operation according to the above-mentioned conventional technique, there are the following problems.

第1に、原子炉圧力容器側の主蒸気系配管1と給水系
配管2の位置的な問題と、これらの配管の水圧試験およ
び洗浄作業の時期的な問題がある。すなわち、狭い原子
炉圧力容器内に機器,配管,サポート,ダクト,電気用
ケーブルトレイ,計装配管等を搬入し、取り付ける原子
力発電設備建設の最盛時に、原子炉圧力容器側の主蒸気
系配管1と給水系配管2とで別々に水圧試験および洗浄
作業を繰り返して行う従来技術では、原子力発電設備全
体の建設管理上の問題が生じる。
Firstly, there are positional problems of the main steam system piping 1 and the water supply system piping 2 on the reactor pressure vessel side, and timing problems of the hydraulic test and cleaning work of these pipings. That is, when the equipment, pipes, supports, ducts, cable trays for electrical equipment, instrumentation pipes, etc. are brought into and installed in a narrow reactor pressure vessel, the main steam system piping 1 on the reactor pressure vessel side is installed at the peak of the nuclear power plant construction. In the conventional technique in which the water pressure test and the cleaning work are separately repeated for the water supply system pipe 2 and the water supply system pipe 2, a problem occurs in the construction management of the entire nuclear power generation facility.

第2に、水圧試験の条件である、配管の温度を規定温
度まで上げることがむずかしい。すなわち、日本電気協
会電気技術規程に規定されている最低使用温度の確認の
ため、配管の温度を規定温度に上昇させる。この配管の
温度を上げるには、配管にハウスボイラの蒸気を通して
行う。しかし、配管の口径が大きく(例えば、主蒸気系
配管は26インチ、給水系配管は20インチ)、従来技術で
は本管より分かれた枝管からハウスボイラの蒸気を入
れ、循環させるようにしている。このため、蒸気の循環
に10時間以上の長時間を要していた。また、前述のごと
く、配管の口径が大きく、配管の経路も長いため、規定
温度に維持することがむずかしく、水圧試験に使用する
用具の準備等を加味すると、延べ数千工数に達し、原子
力発電設備の建設において、この改善が必須条件となっ
ている。
Secondly, it is difficult to raise the temperature of the pipe to the specified temperature, which is the condition of the water pressure test. That is, the temperature of the pipe is raised to the specified temperature in order to confirm the minimum operating temperature specified in the Electrical Engineering Regulations of the Japan Electric Association. To raise the temperature of this pipe, steam from the house boiler is passed through the pipe. However, the diameter of the piping is large (for example, 26 inches for the main steam system piping and 20 inches for the water supply system piping), and in the prior art, the steam of the house boiler is put in from a branch pipe separated from the main pipe and circulated. . Therefore, it takes a long time of 10 hours or more to circulate the steam. In addition, as mentioned above, the diameter of the pipe is large and the route of the pipe is long, so it is difficult to maintain the temperature at the specified temperature. This improvement is a prerequisite for the construction of.

また、第3に閉止キャップを使用する従来技術では、
大口径の配管に取り付けられる閉止キャップの製作,取
り付けに厳密な設計を要し、施工管理についても、本管
に傷つけないようにする等の充分な注意を必要とし、か
つ水圧試験,洗浄完了後の復旧作業においても、同様な
注意が必要である。
Thirdly, in the prior art using a closing cap,
It requires a strict design for the production and installation of a closure cap that can be attached to large-diameter pipes, and construction management needs to be careful not to damage the main pipe, and after a water pressure test and cleaning is completed. Similar precautions are required in the restoration work of.

さらに、第4に前述の水圧試験の回数の関係から、所
要日数,時間を必要とし、原子力発電設備の建設の主要
工程となっている原子炉圧力容器のノズルの最終継なぎ
溶接の時間的余裕がなくなり、混乱を招く可能性があっ
た。
Fourth, due to the number of water pressure tests described above, the required number of days and time are required, and the time margin for the final joint welding of the nozzle of the reactor pressure vessel, which is the main process of the construction of nuclear power generation equipment, is required. Could be confusing.

本発明の目的は、前記従来技術の問題を解決し、原子
炉圧力容器側に取り付けられている主蒸気系配管と給水
系配管の水圧試験および洗浄を、少ない回数で、しかも
確実に行い得る原子力発電設備の配管の試験・洗浄装置
を提供することにある。
An object of the present invention is to solve the above-mentioned problems of the prior art, and to perform a water pressure test and cleaning of the main steam system piping and the water supply system piping, which are mounted on the reactor pressure vessel side, with a small number of times and with certainty nuclear power. It is to provide a test / cleaning device for piping of power generation equipment.

本発明の他の目的は、主蒸気系配管と給水系配管の水
圧試験および洗浄作業を能率よく実施し得る配管の試験
・洗浄方法を提供することにある。
Another object of the present invention is to provide a pipe testing / cleaning method capable of efficiently performing a water pressure test and a cleaning work on a main steam system pipe and a water supply system pipe.

[課題を解決するための手段] 前記目的は、原子炉圧力容器に接続されている配管の
試験・洗浄装置において、原子炉圧力容器の内側の主蒸
気系配管に取り付けられ全部の主蒸気系配管と連絡可能
な第1の連絡配管治具と、原子炉圧力容器の内側の給水
系配管に取り付けられ全部の給水系配管と連絡可能な第
2の連絡配管治具と、該第1,第2の連絡配管治具を連絡
する仕切り弁を有する連絡配管とを設けてなることによ
り、達成される。
[Means for Solving the Problems] In the test / cleaning device for the piping connected to the reactor pressure vessel, all the main steam piping attached to the main steam piping inside the reactor pressure vessel A first connecting pipe jig capable of communicating with the first connecting pipe jig, and a second connecting pipe jig attached to the water supply pipe inside the reactor pressure vessel and capable of connecting with all the water supply pipes; This is achieved by providing a connecting pipe having a sluice valve for connecting the connecting pipe jig.

また、前記の目的は、前記第1,第2の連絡配管治具を
使用し、原子炉圧力容器内で、主蒸気系配管に第1の連
絡配管治具を接続し、給水系配管に第2の連絡配管治具
を接続したのち、該第1,第2の連絡配管治具を仕切り弁
を有する連絡配管で連絡し、配管の試験と洗浄作業のう
ちの少なくとも一つを行なうことにより、達成される。
Further, the above-mentioned object is to use the first and second connecting pipe jigs, connect the first connecting pipe jig to the main steam system pipe, and connect the first connecting pipe jig to the water supply system pipe in the reactor pressure vessel. After connecting the second connecting pipe jig, the first and second connecting pipe jigs are connected by a connecting pipe having a partition valve, and at least one of a pipe test and a cleaning work is performed, To be achieved.

[作用] 原子炉圧力容器の主蒸気系配管と給水系配管の水圧試
験およびその後に行う洗浄時には、既に主蒸気系配管に
は主蒸気系隔離弁と主蒸気第3隔離弁が取り付けられて
おり、給水系配管には給水系隔離弁が取り付けられてい
る。
[Operation] During the water pressure test of the main steam system piping and the water supply system piping of the reactor pressure vessel and the subsequent cleaning, the main steam system isolation valve and the main steam third isolation valve are already attached to the main steam system piping. , A water supply system isolation valve is attached to the water supply system pipe.

ところで、本発明では前記主蒸気系配管と給水系配管
の水圧試験および洗浄時に、原子炉圧力容器内で主蒸気
系配管には第1の連絡配管治具を取り付け、給水系配管
には第2の連絡配管治具を取り付ける。
By the way, in the present invention, at the time of the water pressure test and cleaning of the main steam system pipe and the water supply system pipe, the first connecting pipe jig is attached to the main steam system pipe in the reactor pressure vessel, and the second line is connected to the water supply system pipe. Attach the connecting piping jig.

これにより、主蒸気系配管と給水系配管とは、第1,第
2の連絡配管治具と、これら第1,第2の連絡配管治具間
を連絡して連絡配管と、この連絡配管に設けられた仕切
り弁とを通じて連通させることが可能となる。また、仕
切り弁を閉じることにより、主蒸気系配管側と給水系配
管側とを遮断することも可能となる。
As a result, the main steam system pipe and the water supply system pipe are connected to the first and second connecting pipe jigs and the connecting pipes by connecting the first and second connecting pipe jigs to each other. It becomes possible to communicate with the provided sluice valve. Also, by closing the sluice valve, it is possible to shut off the main steam system piping side and the water supply system piping side.

そこで、主蒸気系配管と給水系配管とを同時に水圧試
験を行う場合には、複数本の主蒸気系配管のそれぞれに
設けられている主蒸気第3隔離弁のうちのいずれか一つ
に加圧ポンプを連結し、他の主蒸気第3隔離弁を閉じ、
全部の主蒸気系隔離弁を開け、仕切り弁を開け、全部の
給水系隔離弁を閉じる。ついで、加圧ポンプにより水圧
をかけると、原子炉圧力容器に取り付けられている主蒸
気系配管と給水系配管の全部が加圧され、したがって主
蒸気系配管と給水系配管とを同時に水圧試験を行うこと
ができる。
Therefore, when performing a water pressure test on the main steam system piping and the water supply system piping at the same time, the main steam third isolation valve provided on each of the plurality of main steam system piping is added. Connect the pressure pump, close the other main steam third isolation valve,
Open all main steam isolation valves, open sluice valves, and close all water supply isolation valves. Then, when water pressure is applied by the pressure pump, all of the main steam system piping and the water supply system piping attached to the reactor pressure vessel are pressurized, so that the main steam system piping and the water supply system piping are simultaneously subjected to the water pressure test. It can be carried out.

次に、主蒸気系配管のみの水圧試験を行う場合には、
仕切り弁を閉じ、前述の要領で主蒸気系配管に水圧をか
ける。
Next, when performing a water pressure test on the main steam system piping only,
Close the sluice valve and apply water pressure to the main steam system piping as described above.

また、給水系配管のみの水圧試験を行う場合には、二
つの方法がある。
There are two methods for conducting a water pressure test on only the water supply system piping.

その一つは、主蒸気第3隔離弁のうちのいずれか一つ
に加圧ポンプを連結し、他の主蒸気第3隔離弁を閉じ、
主蒸気系隔離弁のうちの加圧ポンプが連結されている主
蒸気第3隔離弁と同じ主蒸気系配管の主蒸気系隔離弁の
み開け、他の主蒸気系隔離弁を閉じ、仕切り弁を開け、
全部の給水系隔離弁を閉じ、前記加圧ポンプで水圧をか
け、規定の水圧になったとき、仕切り弁を閉じて給水系
配管の水圧試験を行う。
One of them is to connect a pressurizing pump to one of the main steam third isolation valves and to close the other main steam third isolation valve,
Open only the main steam system isolation valve of the same main steam system piping as the main steam third isolation valve to which the pressurizing pump of the main steam system isolation valve is connected, close the other main steam system isolation valves, and open the sluice valve. open,
All the water supply system isolation valves are closed, water pressure is applied by the pressurizing pump, and when the specified water pressure is reached, the partition valve is closed and a water pressure test of the water supply system piping is performed.

他の一つは、複数本の給水系配管のそれぞれに設けら
れている給水系隔離弁の一つに加圧ポンプを連結し、他
の給水系隔離弁を閉じ、仕切り弁を閉じ、加圧ポンプに
より水圧をかけて行う。
The other one is to connect a pressurizing pump to one of the water supply system isolation valves provided in each of the plurality of water supply system pipes, close the other water supply system isolation valves, close the gate valve, and pressurize. Water pressure is applied by a pump.

前記水圧試験において、最低使用温度の確認のため、
配管の温度を規定温度まで上昇させる場合は、複数本の
主蒸気系配管のうちの1本にハウスボイラを連絡し、こ
の主蒸気系配管の主蒸気第3隔離弁と主蒸気系隔離弁を
開け、他の全部の主蒸気系配管の主蒸気系隔離弁を閉
じ、仕切り弁を開け、全部の給水系隔離弁を閉じ、ハウ
スボイラから蒸気を送り、このハウスボイラに連絡され
た主蒸気系配管を通じて他の主蒸気系配管や給水系配管
に蒸気を送り込む。これにより、配管を極めて短時間で
規定温度に上昇させることができる。
In the water pressure test, for confirmation of the minimum operating temperature,
When raising the temperature of the pipe to the specified temperature, connect the house boiler to one of the multiple main steam system pipes and connect the main steam third isolation valve and the main steam system isolation valve of this main steam system pipe. Open, close all other main steam system isolation valves in main steam system piping, open gate valves, close all water supply system isolation valves, send steam from the house boiler, and contact the main steam system to this house boiler. Sends steam to other main steam system piping and water supply system piping through piping. Thereby, the piping can be raised to the specified temperature in an extremely short time.

前記配管の水圧試験終了後、配管の洗浄を行う場合
は、二つの方法がある。
There are two methods for cleaning the pipe after the completion of the hydraulic test of the pipe.

その一つは、仕切り弁を閉じ、少なくとも一つの給水
系隔離弁を開け、給水系配管を通じて洗浄水を供給し、
満杯になったら仕切り弁を開け、主蒸気系配管に前記洗
浄水を通水する。
One of them is to close the sluice valve, open at least one water supply system isolation valve, and supply cleaning water through the water supply system pipe,
When full, open the sluice valve and pass the washing water through the main steam system piping.

他の一つは、仕切り弁を閉じ、少なくとも1本の主蒸
気系配管の主蒸気第3隔離弁と主蒸気系隔離弁を開け、
主蒸気系配管から洗浄水を供給し、満杯になったら仕切
り弁を開け、給水系配管に前記洗浄水を通水する。
The other one is to close the sluice valve and open the main steam third isolation valve and the main steam isolation valve of at least one main steam system pipe,
The cleaning water is supplied from the main steam system pipe, and when it is full, the sluice valve is opened and the cleaning water is passed through the water supply system pipe.

そのいずれによっても、全部の主蒸気系配管と全部の
給水系配管とを、同時に洗浄することができる。
By any of them, all the main steam system pipes and all the water supply system pipes can be cleaned at the same time.

[実施例] 以下、本発明の実施例を図面により説明する。[Embodiment] An embodiment of the present invention will be described below with reference to the drawings.

第1図は本発明の一実施例を示すもので、主蒸気系配
管および給水系配管に第1,第2の連絡配管治具を取り付
けた状態を示す系統図、第2図は第1,第2の連絡配管治
具の一例を示す一部拡大断面図である。
FIG. 1 shows an embodiment of the present invention, and is a system diagram showing a state in which the first and second connecting pipe jigs are attached to the main steam system pipe and the water supply system pipe, and FIG. It is a partially expanded sectional view which shows an example of a 2nd connection piping jig.

これらの図に示す実施例では、第1図に示すように、
原子炉圧力容器8の内部において、主蒸気系配管1には
第1の連絡配管治具18が取り付けられ、給水系配管2に
は第2の連絡配管治具19が取り付けられている。
In the embodiment shown in these figures, as shown in FIG.
Inside the reactor pressure vessel 8, a first connecting pipe jig 18 is attached to the main steam system pipe 1, and a second connecting pipe jig 19 is attached to the water supply system pipe 2.

前記第1の連絡配管治具18と第2の連絡配管治具19と
は、連絡配管20により連絡されている。この連絡配管20
には、仕切り弁21が設けられている。
The first connecting pipe jig 18 and the second connecting pipe jig 19 are connected by a connecting pipe 20. This connection pipe 20
A sluice valve 21 is provided in the.

前記第1,第2の連絡配管治具18,19は、第2図に示す
ように、ウオータジャケット22と、これに配管の数だけ
設けられたプラグ23と、前記ウオータジャケット22の外
側から配管にプラグ23を押し込む押しボルト24と、この
押しボルト用のナット25とを有して構成されている。
As shown in FIG. 2, the first and second connecting pipe jigs 18 and 19 include a water jacket 22, plugs 23 provided in the same number as the number of pipes, and a pipe from the outside of the water jacket 22. And a push bolt (24) for pushing the plug (23) into it and a nut (25) for this push bolt.

前記ウオータジャケット22には、前記連絡配管20の先
端部が臨んでいる。
The water jacket 22 faces the tip of the communication pipe 20.

前記プラグ23は、前記ウオータジャケット22に設けら
れ、かつ配管の軸方向に出没可能に取り付けられてい
る。
The plug 23 is provided on the water jacket 22 and is attached so as to be retractable in the axial direction of the pipe.

前記押しボルト24は、ウオータジャケット22の外側壁
に固定されたナット25を介して当該プラグ23を配管の先
端部に押し込み、密接に嵌合させるようになっている。
The push bolt 24 pushes the plug 23 into the distal end portion of the pipe via a nut 25 fixed to the outer wall of the water jacket 22 so that the plug 23 is closely fitted.

そして、第2図に示す第1,第2の連絡配管治具18,19
では、前記ウオータジャケット22を通じて、原子炉圧力
容器8に取り付けられかつ第2図中では符号26で代表す
る配管に装着されたプラグ23から連絡配管20へ、また反
対に連絡配管20からプラグ23を介して配管26へ水圧試験
用の水や蒸気、または洗浄水を流すようになっている。
Then, the first and second connecting pipe jigs 18, 19 shown in FIG.
Then, from the plug 23 attached to the reactor pressure vessel 8 through the water jacket 22 and attached to the pipe represented by reference numeral 26 in FIG. 2 to the connecting pipe 20, and conversely, the connecting pipe 20 to the plug 23. Water, steam, or cleaning water for a water pressure test is made to flow through the pipe 26 via the pipe.

前記実施例の配管の試験・洗浄装置を使用して、原子
炉圧力容器の主蒸気系配管と給水系配管の水圧試験およ
び洗浄作業を次のように実施する。
Using the pipe testing / cleaning apparatus of the above-described embodiment, a water pressure test and a cleaning operation for the main steam system piping and the water supply system piping of the reactor pressure vessel are carried out as follows.

原子炉圧力容器8に接続されている主蒸気系配管1と
給水系配管2の水圧試験およびその後に行う洗浄時に
は、既に主蒸気系配管1には主蒸気系隔離弁4と主蒸気
第3隔離弁5が取り付けられており、給水系配管2には
給水系隔離弁3が取り付けられている。
During the water pressure test of the main steam system piping 1 and the water supply system piping 2 connected to the reactor pressure vessel 8 and the subsequent cleaning, the main steam system isolation valve 4 and the main steam third isolation are already installed in the main steam system piping 1. A valve 5 is attached, and a water supply system isolation valve 3 is attached to the water supply system pipe 2.

ところで、本発明では前記主蒸気系配管1と給水系配
管2の水圧試験および洗浄時に、原子炉圧力容器8内で
主蒸気系配管1には第1の連絡配管治具18を取り付け、
給水系配管2には第2の連絡配管治具19を取り付ける。
By the way, in the present invention, at the time of the water pressure test and cleaning of the main steam system pipe 1 and the water supply system pipe 2, the first connecting pipe jig 18 is attached to the main steam system pipe 1 in the reactor pressure vessel 8.
A second connecting pipe jig 19 is attached to the water supply pipe 2.

これにより、主蒸気系配管1と給水系配管2とは、第
1,第2の連絡配管治具18,19と、これら第1,第2の連絡
配管治具18,19間を連絡している連絡配管20と、この連
絡配管20に設けられた仕切り弁21とを通じて連通させる
ことが可能となる。また、仕切り弁21を閉じることによ
り、主蒸気系配管1側と給水系配管2側とを遮断するこ
とも可能となる。
As a result, the main steam system pipe 1 and the water supply system pipe 2 are
The first and second connecting pipe jigs 18 and 19, the connecting pipe 20 connecting the first and second connecting pipe jigs 18 and 19, and the sluice valve 21 provided in the connecting pipe 20. It becomes possible to communicate through and. Further, by closing the sluice valve 21, it becomes possible to shut off the main steam system pipe 1 side and the water supply system pipe 2 side.

ついで、配管の水圧試験および洗浄は、次のようにし
て実施する。
Then, the water pressure test and cleaning of the pipes are performed as follows.

(1)主蒸気系配管1と給水系配管2とを同時に水圧試
験を行う場合には、複数本の主蒸気系配管1のそれぞれ
に設けられている主蒸気第3隔離弁5のうちのいずれか
一つに加圧ポンプ(図示省略)を連結し、他の主蒸気第
3隔離弁5を閉じ、全部の主蒸気系隔離弁4を開け、仕
切り弁21を開け、全部の給水系隔離弁3を閉じる。つい
で、加圧ポンプにより水圧をかけると、原子炉圧力容器
8に取り付けられている主蒸気系配管1と給水系配管2
の全部が加圧され、したがって主蒸気系配管1と給水系
配管2とを同時に水圧試験を行うことができる。
(1) When performing a water pressure test on the main steam system pipe 1 and the water supply system pipe 2 at the same time, which one of the main steam third isolation valves 5 is provided for each of the plurality of main steam system pipes 1 A pressure pump (not shown) is connected to one of them, the other main steam third isolation valve 5 is closed, all the main steam system isolation valves 4 are opened, the partition valves 21 are opened, and all the water supply system isolation valves are opened. Close 3. Then, when water pressure is applied by a pressure pump, a main steam system pipe 1 and a water supply system pipe 2 attached to the reactor pressure vessel 8
Is pressurized, so that the main steam system pipe 1 and the water supply system pipe 2 can be simultaneously subjected to the water pressure test.

(2)主蒸気系配管1のみの水圧試験を行う場合には、
仕切り弁21を閉じ、前述の要領で主蒸気系配管1に水圧
をかける。
(2) When conducting a water pressure test on the main steam system piping 1 only,
The sluice valve 21 is closed, and water pressure is applied to the main steam system pipe 1 as described above.

(3)給水系配管2のみの水圧試験を行う場合には、二
つの方法がある。
(3) There are two methods for conducting a water pressure test on only the water supply system pipe 2.

(i) 主蒸気第3隔離弁5のうちのいずれか一つに加
圧ポンプを連結し、他の主蒸気第3隔離弁5を閉じ、主
蒸気系隔離弁4のうちの加圧ポンプが連結されている主
蒸気第3隔離弁5と同じ主蒸気系配管1の主蒸気系隔離
弁4のみ開け、他の主蒸気系隔離弁4を閉じ、仕切り弁
21を開け、全部の給水系隔離弁3を閉じ、前記加圧ポン
プで水圧をかけ、規定の水圧になったとき、仕切り弁21
を閉じて給水系配管2の水圧試験を行う。
(I) A pressurizing pump is connected to any one of the main steam third isolation valves 5, the other main steam third isolating valves 5 are closed, and the pressurizing pump of the main steam system isolation valves 4 is Only the main steam system isolation valve 4 of the same main steam system piping 1 as the connected main steam third isolation valve 5 is opened, the other main steam system isolation valve 4 is closed, and the sluice valve
21 is opened, all the water supply system isolation valves 3 are closed, water pressure is applied by the pressurizing pump, and when the specified water pressure is reached, the sluice valve 21
Is closed and a water pressure test of the water supply system pipe 2 is performed.

(ii) 複数本の給水系配管2のそれぞれに設けられて
いる給水系隔離弁3の一つに加圧ポンプを連結し、他の
給水系隔離弁3を閉じ、仕切り弁21を閉じ、加圧ポンプ
により水圧をかけて行う。
(Ii) A pressurizing pump is connected to one of the water supply system isolation valves 3 provided in each of the plurality of water supply system pipes 2, the other water supply system isolation valve 3 is closed, and the sluice valve 21 is closed. Water pressure is applied by a pressure pump.

(4)前記配管の水圧試験において、最低使用温度の確
認のため、配管の温度を規定温度まで上昇させる場合
は、次のようにして行う。
(4) In the water pressure test of the pipe, in order to confirm the minimum operating temperature, when the temperature of the pipe is raised to the specified temperature, it is performed as follows.

すなわち、複数本の主蒸気系配管1のうちの1本にハ
ウスボイラ(図示省略)を連絡し、この主蒸気系配管1
の主蒸気第3隔離弁5と主蒸気系隔離弁4を開け、他の
全部の主蒸気系配管1の主蒸気系隔離弁4を閉じ、仕切
り弁21を開け、全部の給水系隔離弁3を閉じ、ハウスボ
イラからこれに連絡された主蒸気系配管1を通じて他の
主蒸気系配管1や給水系配管2に蒸気を送り込み、この
蒸気により配管を加熱する。これにより、配管を極めて
短時間で規定温度に上昇させることができる。
That is, a house boiler (not shown) is connected to one of the plurality of main steam system pipes 1,
Main steam third isolation valve 5 and main steam system isolation valve 4 are opened, all other main steam system isolation valves 4 of main steam system piping 1 are closed, partition valves 21 are opened, and all water supply system isolation valves 3 , The steam is sent from the house boiler to the other main steam system piping 1 and the water supply system piping 2 through the main steam system piping 1 connected thereto, and the steam is heated by the steam. Thereby, the piping can be raised to the specified temperature in an extremely short time.

(5)前記配管の水圧試験終了後、配管の洗浄を行う場
合は、二つの方法がある。
(5) There are two methods for cleaning the pipe after the completion of the hydraulic test of the pipe.

(i) 仕切り弁21を閉じ、少なくとも一つの給水隔離
弁3を開け、給水系配管2を通じて洗浄水を供給し、満
杯になったら仕切り弁21を開け、主蒸気系配管1に前記
洗浄水を通水する。
(I) The sluice valve 21 is closed, at least one water supply isolation valve 3 is opened, washing water is supplied through the water supply system pipe 2, and when the sluice valve 21 is full, the sluice valve 21 is opened and the main steam system pipe 1 is filled with the washing water. Pass water.

(ii) 仕切り弁21を閉じ、少なくとも1本の主蒸気系
配管1の主蒸気第3隔離弁5と主蒸気系隔離弁4を開
け、主蒸気系配管1から洗浄水を供給し、満杯になった
ら仕切り弁21を開け、給水系配管2に前記洗浄水を通水
する。前記(i),(ii)のいずれによっても、全部の
主蒸気系配管1と全部の給水系配管2とを、同時に洗浄
することができる。
(Ii) The sluice valve 21 is closed, the main steam third isolation valve 5 and the main steam isolation valve 4 of at least one main steam system pipe 1 are opened, and cleaning water is supplied from the main steam system pipe 1 to fill up the space. When this happens, the sluice valve 21 is opened, and the washing water is passed through the water supply system pipe 2. Both of the above (i) and (ii) can simultaneously clean all the main steam system pipes 1 and all the water supply system pipes 2.

[発明の効果] 以上説明した本発明装置によれば、原子炉圧力容器に
接続されている配管の試験・洗浄装置において、原子炉
圧力容器の内側の主蒸気系配管に取り付けられ全部の主
蒸気系配管と連絡可能な第1の連絡配管治具と、原子炉
圧力容器の内側の給水系配管に取り付けられ全部の給水
系配管と連絡可能な第2の連絡配管治具と、該第1,第2
の連絡配管治具を連絡する仕切り弁を有する連絡配管と
を設けてなり、第1,第2の連絡配管治具間の連絡配管に
設けられた仕切り弁と、原子炉圧力容器側に取り付けら
れた主蒸気系配管に設けられている主蒸気系隔離弁およ
び主蒸気第3隔離弁と、同じく原子炉圧力容器側に取り
付けられた給水系配管に設けられている給水系隔離弁と
を、作業目的に合わせて開閉操作することにより、全部
の主蒸気系配管と全部の給水系配管の水圧試験を同時
に、しかも確実に行うことができ、また必要により主蒸
気系配管と給水系配管とを別々に水圧試験を行うことも
でき、さらに配管の水圧試験終了後の洗浄も同時にかつ
確実に行い得る効果がある。その結果、水圧試験および
洗浄作業の回数を大幅に削減することが可能となり、原
子炉格納容器に色々な部材を取り付ける工事と、配管の
水圧試験および洗浄作業が時期的に重なっても、前記工
事と作業を円満に完了させ得る効果もある。
[Effects of the Invention] According to the apparatus of the present invention described above, in a test / cleaning apparatus for piping connected to a reactor pressure vessel, all main steam attached to the main steam system piping inside the reactor pressure vessel A first connecting pipe jig capable of communicating with the system pipe, and a second connecting pipe jig attached to the water supply system pipe inside the reactor pressure vessel and capable of communicating with all the water supply system pipes; Second
And a connecting valve having a sluice valve for connecting the connecting pipe jig, and a sluice valve provided in the connecting pipe between the first and second connecting pipe jigs and attached to the reactor pressure vessel side. The main steam system isolation valve and the main steam third isolation valve provided in the main steam system pipe, and the water supply system isolation valve provided in the water supply system pipe also attached to the reactor pressure vessel side are operated. By opening and closing according to the purpose, it is possible to perform a water pressure test on all the main steam system piping and all the water supply system piping simultaneously and reliably, and if necessary, separate the main steam system piping and the water supply system piping. It is also possible to conduct a water pressure test on the pipes and to wash the pipes at the same time and reliably after the completion of the water pressure test. As a result, the number of water pressure tests and cleaning operations can be significantly reduced, and even if the water pressure tests and cleaning operations for pipes and the installation of various components in the reactor containment vessel overlap in time, And there is also an effect that the work can be completed satisfactorily.

また、本発明装置によれば、選択された主蒸気系配置
にハウスボイラを連絡し、他の主蒸気系配管の主蒸気系
隔離弁を閉じ、仕切り弁を開け、全部の給水系隔離弁を
閉じ、前記ハウスボイラからこれと連絡された主蒸気系
配管を通じて蒸気を送ることにより、全部の主蒸気系配
管と、全部の給水系配管にハウスボイラから蒸気を送り
込み、その蒸気で加熱できるので、水圧試験において配
管の温度を規定温度まで上昇させる工程を極めて短時間
で実施し得る効果もある。
Further, according to the device of the present invention, the house boiler is connected to the selected main steam system arrangement, the main steam system isolation valves of the other main steam system pipes are closed, the partition valves are opened, and all the water supply system isolation valves are opened. Closed, by sending steam from the house boiler through the main steam system piping in communication with this, all main steam system piping and all the water supply system piping are fed with steam from the house boiler and can be heated by the steam, There is also an effect that the step of raising the temperature of the pipe to the specified temperature in the water pressure test can be carried out in an extremely short time.

さらに、本発明方法によれば、前記第1,第2の連絡配
管治具を使用して、原子炉圧力容器に接続されている主
蒸気系配管と給水系配管の水圧試験および洗浄作業を能
率よく行い得る効果がある。
Further, according to the method of the present invention, by using the first and second connecting piping jigs, the hydraulic pressure test and cleaning work of the main steam system piping and the water supply system piping connected to the reactor pressure vessel can be performed efficiently. There is an effect that can be done well.

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

第1図は本発明の一実施例を示すもので、主蒸気系配管
側および給水系配管側に第1,第2の連絡配管治具を取り
付けた状態を示す系統図、第2図は第1,第2の連絡配管
治具の一例を示す一部拡大断面図、第3図は原子力発電
設備の縦断面図、第4図は従来技術を示す系統図であ
る。 1,14……主蒸気系配管、2,15……給水系配管、3……給
水系隔離弁、4……主蒸気系隔離弁、5……主蒸気第3
隔離弁、8……原子炉圧力容器、18,19……第1,第2の
連絡配管治具、20……連絡配管、21……仕切り弁。
FIG. 1 shows an embodiment of the present invention. A system diagram showing a state in which first and second connecting pipe jigs are attached to the main steam system piping side and the water supply system piping side, and FIG. FIG. 3 is a partially enlarged sectional view showing an example of the first and second connecting piping jigs, FIG. 3 is a vertical sectional view of a nuclear power generation facility, and FIG. 4 is a system diagram showing a conventional technique. 1,14 …… Main steam system piping, 2,15 …… Water supply system piping, 3 …… Water supply system isolation valve, 4 …… Main steam system isolation valve, 5 …… Main steam third
Isolation valve, 8 ...... Reactor pressure vessel, 18, 19 ...... 1st and 2nd connecting pipe jig, 20 ...... Connecting pipe, 21 ...... Gate valve.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 山根 洋一 茨城県日立市幸町3丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 佐藤 重士 茨城県日立市幸町3丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 安藤 操 茨城県日立市会瀬町2丁目9番1号 株式 会社日立エンジニアリングサービス内 (56)参考文献 特開 昭63−175798(JP,A) 実開 平1−84097(JP,U) ─────────────────────────────────────────────────── ─── Continued Front Page (72) Inventor Yoichi Yamane 3-1-1, Saiwaicho, Hitachi, Ibaraki Hitachi Ltd. Hitachi factory (72) Inventor Shigeshi Sato 3-chome, Hitachi, Hitachi 1-1 No. 1 Hitachi Ltd., Hitachi Works (72) Inventor Misao Ando 2-9-1 Aisemachi, Hitachi City, Ibaraki Hitachi Engineering Service Co., Ltd. (56) Reference JP-A-63-175798 (JP , A) Actual Kaihei 1-84097 (JP, U)

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】原子炉圧力容器に接続されている配管の試
験・洗浄装置において、原子炉圧力容器の内側の主蒸気
系配管に取り付けられ全部の主蒸気系配管と連絡可能な
第1の連絡配管治具と、原子炉圧力容器の内側の給水系
配管に取り付けられ全部の給水系配管と連絡可能な第2
の連絡配管治具と、該第1,第2の連絡配管治具を連絡す
る仕切り弁を有する連絡配管とを設けてなることを特徴
とする原子力発電設備の配管の試験・洗浄装置。
1. In a test / cleaning device for a pipe connected to a reactor pressure vessel, a first communication which is attached to a main steam system pipe inside a reactor pressure vessel and can communicate with all main steam system pipes. Piping jig and water supply system piping inside the reactor pressure vessel that can be connected to all water supply system piping No. 2
And a connecting pipe having a sluice valve for connecting the first and second connecting pipe jigs to each other.
【請求項2】請求項1記載の第1,第2の連絡配管治具を
使用し、原子炉圧力容器内で、主蒸気系配管に第1の連
絡配管治具を接続し、給水系配管に第2の連絡配管治具
を接続したのち、該第1,第2の連絡配管治具を仕切り弁
を有する連絡配管で連絡し、配管の試験と洗浄作業のう
ちの少なくとも一つを行なうことを特徴とする原子力発
電設備の配管の試験・洗浄方法。
2. The first and second connecting pipe jigs according to claim 1, wherein the first connecting pipe jig is connected to the main steam system pipe in the reactor pressure vessel, and the water supply system pipe is connected. After connecting the second connecting pipe jig to, connect the first and second connecting pipe jigs with the connecting pipe having a sluice valve, and perform at least one of testing and cleaning of the pipe. A method for testing and cleaning pipes of nuclear power generation equipment characterized by.
JP1304716A 1989-11-27 1989-11-27 Test / cleaning device and test / cleaning method for nuclear power plant piping Expired - Lifetime JPH087273B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1304716A JPH087273B2 (en) 1989-11-27 1989-11-27 Test / cleaning device and test / cleaning method for nuclear power plant piping

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1304716A JPH087273B2 (en) 1989-11-27 1989-11-27 Test / cleaning device and test / cleaning method for nuclear power plant piping

Publications (2)

Publication Number Publication Date
JPH03167497A JPH03167497A (en) 1991-07-19
JPH087273B2 true JPH087273B2 (en) 1996-01-29

Family

ID=17936352

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1304716A Expired - Lifetime JPH087273B2 (en) 1989-11-27 1989-11-27 Test / cleaning device and test / cleaning method for nuclear power plant piping

Country Status (1)

Country Link
JP (1) JPH087273B2 (en)

Also Published As

Publication number Publication date
JPH03167497A (en) 1991-07-19

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