JPH0679704B2 - Reactor system piping cleaning method - Google Patents
Reactor system piping cleaning methodInfo
- Publication number
- JPH0679704B2 JPH0679704B2 JP61290351A JP29035186A JPH0679704B2 JP H0679704 B2 JPH0679704 B2 JP H0679704B2 JP 61290351 A JP61290351 A JP 61290351A JP 29035186 A JP29035186 A JP 29035186A JP H0679704 B2 JPH0679704 B2 JP H0679704B2
- Authority
- JP
- Japan
- Prior art keywords
- pipe
- pressure vessel
- main steam
- reactor pressure
- piping
- 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
Links
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- Cleaning In General (AREA)
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、原子力発電所等に設置される原子炉系の配管
洗浄方法に係り、特に主蒸気配管および復水給水配管の
配管洗浄方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Field of Industrial Application) The present invention relates to a method for cleaning a pipe of a nuclear reactor system installed in a nuclear power plant or the like, and particularly to a main steam pipe and a condensate water supply pipe. Related to the pipe cleaning method.
(従来の技術) 原子炉圧力容器に接続される原子炉系の配管系統は一般
に第2図に例示するように構成される。すなわち、原子
炉圧力容器1内で発生した蒸気は、主蒸気配管2を通り
図示しない発電機を駆動させる蒸気タービンへ導入され
蒸気タービンを回転せしめた後に、その直下に配設した
復水器3内において凝縮されて復水となる。この復水器
3内にて凝縮された復水は復水系ポンプ4および復水給
水ポンプ5によって復水給水配管6を介して移送され、
給水加熱器7を経て再び原子炉圧力容器1内に還流され
る。そのため、主蒸気系および復水給水系配管は、原子
炉圧力容器1を中心にして循環流路を形成している。し
たがって、主蒸気系および復水給水系の両配管系は、組
立完了後、同時に配管洗浄が実施される。(Prior Art) A piping system of a reactor system connected to a reactor pressure vessel is generally configured as illustrated in FIG. That is, the steam generated in the reactor pressure vessel 1 passes through the main steam pipe 2 and is introduced into a steam turbine for driving a generator (not shown) to rotate the steam turbine, and then the condenser 3 disposed immediately below the steam turbine 3. It is condensed inside and becomes condensed water. Condensate condensed in the condenser 3 is transferred by the condensate system pump 4 and the condensate water supply pump 5 through the condensate water supply pipe 6.
It is returned to the reactor pressure vessel 1 again via the feed water heater 7. Therefore, the main steam system and the condensate water supply system piping form a circulation flow path around the reactor pressure vessel 1. Therefore, for both the main steam system and the condensate water supply system, the pipes are cleaned at the same time after the assembly is completed.
そして、洗浄作業を行なう際に循環流路の途中に介在す
る機器で洗浄液を通過させることが好ましくない機器に
大しては適宜バイパスを利用し、または仮設のバイパス
配管を設置して、機器をバイパスし、循環流路を形成す
る。例えば蒸気タービン廻りにおいては、主蒸気止め弁
8の一次側から分岐し、タービンバイパス弁9を経て直
接復水器3に至るタービンバイパス配管10を利用して洗
浄液の循環流路とする。Then, when the cleaning operation is performed, a bypass is appropriately used for a device that is not preferable to pass the cleaning liquid with a device interposed in the circulation flow path, or a temporary bypass pipe is installed to bypass the device. , Forming a circulation channel. For example, around the steam turbine, a turbine bypass pipe 10 that branches from the primary side of the main steam stop valve 8 and reaches the condenser 3 directly via the turbine bypass valve 9 is used as a circulation passage for the cleaning liquid.
また、構造的に洗浄が困難である復水給水ポンプ5等の
機器は、バイパス用仮設配管12によってバイパスを形成
する。一方、原子炉圧力容器1廻りの主蒸気配管2と復
水給水配管6とは原子炉圧力容器1を経由することな
く、連通用仮設配管13によって接続される。すなわち、
主蒸気配管2および復水給水配管6が原子炉圧力容器1
と取合う部分を構成する最終スプール配管は取外された
状態で両者は仮に接続される。Further, equipment such as the condensate water supply pump 5 which is structurally difficult to clean forms a bypass by the bypass temporary pipe 12. On the other hand, the main steam pipe 2 around the reactor pressure vessel 1 and the condensate water supply pipe 6 are connected by a temporary piping 13 for communication without passing through the reactor pressure vessel 1. That is,
Main steam pipe 2 and condensate water supply pipe 6 are reactor pressure vessels 1.
The final spool pipe constituting the part to be connected with is temporarily connected with the pipe removed.
上記の通り仮設のバイパス配管を形成する等の手段によ
って主蒸気配管2および復水給水配管6は接続され循環
流路を形成する。As described above, the main steam pipe 2 and the condensate water supply pipe 6 are connected by means such as forming a temporary bypass pipe to form a circulation flow path.
次に、この循環流路を洗浄する操作について具体的に説
明する。Next, the operation of cleaning the circulation channel will be specifically described.
まず、循環流路を構成する配管に漏れ等の欠陥が存在し
ないことを各種配管検査で確認後、洗浄装置14で調製し
た洗浄液を注水用仮設配管15を経由して移送し、循環流
路内に注入する。First, after confirming by various pipe inspections that there are no defects such as leaks in the piping that constitutes the circulation flow path, the cleaning liquid prepared by the cleaning device 14 is transferred through the temporary water injection piping 15, and inside the circulation flow path. Inject.
ここで、洗浄装置14は、第3図に例示するように、洗浄
薬剤を純水に溶解せしめ貯蔵する薬剤溶解タンク17と、
薬剤の溶媒となる純水を貯蔵する純粋貯蔵タンク18と、
薬剤溶液を純水中に注入する薬注ポンプ19と、薬剤溶液
と純水とを均一に混合するミキシングヒータ20と、均一
に混合して調製された洗浄液を移送する洗浄液ポンプ21
とから構成される。洗浄液は注水用仮設配管15を通り、
第2図に示すように復水系ポンプ4の二次側に配設した
出口逆止弁16のボンネット部から循環流路内に注入され
る。Here, as shown in FIG. 3, the cleaning device 14 includes a chemical dissolution tank 17 for storing a cleaning chemical by dissolving it in pure water,
A pure storage tank 18 for storing pure water serving as a solvent for the drug,
A chemical injection pump 19 for injecting a chemical solution into pure water, a mixing heater 20 for uniformly mixing the chemical solution and pure water, and a cleaning liquid pump 21 for transferring a cleaning liquid prepared by uniform mixing.
Composed of and. The cleaning liquid passes through the temporary pipe 15 for water injection,
As shown in FIG. 2, it is injected into the circulation passage from the bonnet portion of the outlet check valve 16 arranged on the secondary side of the condensate system pump 4.
注入された洗浄液は、復水系ポンプ4によって循環流路
内を循環し配管内壁に固着したスケールおよび油分等の
付着物を洗浄除去する。所定時間洗浄運転を継続し、系
内が規定の洗浄度に達した時点で系内に残留する使用済
の洗浄液は、主蒸気止め弁8に接続した排出用仮設配管
22を通り排出され、第4図に示すように処理装置23に導
入される。処理装置23は、使用済洗浄液をまず中和槽24
にて中和処理後、沈澱槽25にてスケール分等を沈澱分離
し、清澄水のみを系外に排出する。The injected cleaning liquid is circulated in the circulation flow path by the condensate system pump 4 to clean and remove the adhered substances such as scale and oil adhered to the inner wall of the pipe. After the cleaning operation is continued for a predetermined time, the used cleaning liquid remaining in the system when the system reaches the specified cleaning degree is the temporary pipe for discharge connected to the main steam stop valve 8.
It is discharged through 22 and is introduced into the processing device 23 as shown in FIG. The processing device 23 first uses the used cleaning liquid in the neutralization tank 24.
After the neutralization treatment at, the scale component and the like are precipitated and separated in the precipitation tank 25, and only clear water is discharged out of the system.
上記洗浄作業の完了後、洗浄液の循環流路を構成してい
たバイパス用仮設配管12、注水用仮設配管15、排出用仮
設配管22、連通用仮設配管13を撤去し、原子炉圧力容器
1と取合う主蒸気配管2の4本の最終スプール配管と、
復水給水配管6の6本の最終スプール配管および付設さ
れる各配管サポートを正規の位置において組立て、溶接
接合によって取付けた後、さらに次の検査工程で実施す
る原子炉圧力容器1の耐圧試験のバウンダリ構成等の準
備作業を引き続き実施する。After the above cleaning work is completed, the bypass temporary pipe 12, the water injection temporary pipe 15, the discharge temporary pipe 22, and the communication temporary pipe 13 that constitute the circulation channel of the cleaning liquid are removed, and the reactor pressure vessel 1 and 4 final spool pipes of main steam pipe 2
After assembling the six final spool pipes of the condensate water supply pipe 6 and the respective attached pipe supports at regular positions and attaching them by welding and joining, the pressure resistance test of the reactor pressure vessel 1 to be carried out in the next inspection step is performed. Continue preparation work such as boundary composition.
(発明が解決しようとする問題点) 従来の配管洗浄方法においては、主蒸気配管および復水
給水配管の最終スプール配管を形成する前の段階で両者
を連通用仮設配管で接続し、洗浄水の循環流路を形成し
ていたため、循環洗浄作業が終了するまでは最終スプー
ル配管を取付けることができなかった。最終スプール配
管は、主蒸気配管、復水給水配管の原子炉圧力容器と取
合部を構成し、原子炉圧力容器の耐圧試験を実施する前
にその取付が完了する必要がある。ところで、最終スプ
ール配管は、主蒸気配管用が4系統あり、一方復水給水
配管用が6系統あり、さらに付設する配管架台、サポー
トを含めるとその組立から溶接に要する作業量は膨大で
あり、そのため配管洗浄作業後の復旧工期が長期化する
傾向があった。また、最終スプール配管の溶接が完了し
ないとバウンダリが形成されないため、原子炉圧力容器
の耐圧試験は実施できない。したがって、復旧工期の長
期化がプラント建設のクリティカルパスを長期化する問
題点があった。(Problems to be Solved by the Invention) In the conventional pipe cleaning method, the main steam pipe and the condensate water supply pipe are connected to each other by a temporary pipe for communication before the final spool pipe is formed, Since the circulation passage was formed, the final spool pipe could not be attached until the circulation cleaning work was completed. The final spool pipe constitutes a connection part with the reactor pressure vessel of the main steam pipe and the condensate water supply pipe, and its installation must be completed before carrying out the pressure resistance test of the reactor pressure vessel. By the way, the final spool piping has four systems for main steam piping, while there are six systems for condensate water supply piping, and when the piping stand and support attached are included, the amount of work required from assembly to welding is enormous. Therefore, there was a tendency for the recovery period after the pipe cleaning work to be prolonged. Further, since the boundary is not formed unless the welding of the final spool pipe is completed, the pressure resistance test of the reactor pressure vessel cannot be performed. Therefore, there is a problem in that the lengthening of the recovery period lengthens the critical path for plant construction.
本発明は上記の問題点を解決するために発案されたもの
であり、配管洗浄作業後の復旧工期を短縮させることに
よってプラント全体の建設工期を短縮させることのでき
る原子炉系の配管洗浄方法を提供することを目的とす
る。The present invention has been devised to solve the above problems, and a method for cleaning the piping of a reactor system that can shorten the construction period of the entire plant by shortening the recovery period after the pipe cleaning work. The purpose is to provide.
(問題点を解決するための手段) 本発明に係る原子炉系の配管洗浄方法は、主蒸気配管お
よび復水給水配管が原子炉圧力容器と取り合う部分を構
成する最終スプール配管を予め原子炉圧力容器に接合す
る一方、原子炉圧力容器に接合した主蒸気配管の開口部
を原子炉圧力容器内に配設した仮設配管で相互に連通す
るように接続し、さらに主蒸気配管の逃し安全弁管台と
原子炉圧力容器入口部における復水給水配管の逆止弁と
を仮設配管で接続することによって主蒸気配管および復
水給水配管を環状に接続して洗浄液の循環流路を形成し
た後に、洗浄液を前記循環流路内に注入し、所定時間洗
浄液を循環することを特徴とする。(Means for Solving the Problems) In the reactor system pipe cleaning method according to the present invention, the final spool pipe constituting the portion where the main steam pipe and the condensate feedwater pipe are combined with the reactor pressure vessel is pre-reacted with the reactor pressure. While connecting to the vessel, the opening of the main steam pipe joined to the reactor pressure vessel is connected so as to communicate with each other by a temporary pipe installed inside the reactor pressure vessel, and the relief safety valve base of the main steam pipe is connected. And the non-return valve of the condensate water supply pipe at the inlet of the reactor pressure vessel are connected by a temporary pipe to connect the main steam pipe and the condensate water supply pipe in an annular shape to form a circulation passage for the cleaning liquid, and then the cleaning liquid. Is injected into the circulation channel, and the cleaning liquid is circulated for a predetermined time.
(作用) 上記構成の配管洗浄方法によれば、原子炉圧力容器廻り
の配管系を構成する主蒸気配管および復水給水配管の双
方の最終スプール配管が予め原子炉圧力容器に接合され
ており、この状態で主蒸気配管と復水給水配管とが仮設
配管で接続され、環状の循環流路を形成しているため、
所定の循環洗浄作業の終了後における復旧作業が従来方
法と比較して大幅に簡素化される。すなわち、最終スプ
ール配管の組立溶接が不要となり、少数の仮設配管の撤
去のみで復旧作業が完了し、直ちに原子炉圧力容器の耐
圧試験に移行することが容易である。(Operation) According to the pipe cleaning method of the above configuration, the final spool pipes of both the main steam pipe and the condensate water supply pipe that form the piping system around the reactor pressure vessel are joined in advance to the reactor pressure vessel, In this state, the main steam pipe and the condensate water supply pipe are connected by a temporary pipe to form an annular circulation flow path,
The recovery work after the completion of the predetermined circulation cleaning work is greatly simplified as compared with the conventional method. That is, assembling and welding of the final spool pipe is not required, the recovery work is completed by removing only a small number of temporary pipes, and it is easy to immediately shift to the pressure resistance test of the reactor pressure vessel.
また、原子炉圧力容器に接合した主蒸気配管の開口部
を、一対毎に原子炉圧力容器内に配設した仮設配管で相
互に連通するよう接続しているため、洗浄液が一対にな
った主蒸気配管の最終スプール配管内にも流通すること
により、洗浄対象区域を拡大することができる。Further, since the openings of the main steam pipes joined to the reactor pressure vessel are connected to each other by the temporary pipes arranged in the reactor pressure vessel so that they communicate with each other, the main cleaning liquid becomes a pair. The area to be cleaned can be expanded by circulating the steam in the final spool piping of the steam piping.
(実施例) 次に、本発明に係る原子炉系の配管洗浄方法の一実施例
を添付図面を参照して説明する。(Embodiment) Next, one embodiment of a method for cleaning a pipe of a reactor system according to the present invention will be described with reference to the accompanying drawings.
第1図は本発明方法を実施する場合の配管構成例を示す
系統図であり、第2図に示す従来例と同一の要素、部品
には同一符号を付して詳細な説明は省略する。FIG. 1 is a system diagram showing an example of a piping configuration for carrying out the method of the present invention. The same elements and parts as those in the conventional example shown in FIG. 2 are designated by the same reference numerals, and detailed description thereof will be omitted.
本発明方法による洗浄の対象となる配管系は、原子炉圧
力容器1に接合した主蒸気配管最終スプール配管26と、
原子炉格納容器27壁の内外に配設された隔離弁28,29
と、主蒸気配管2と主蒸気止め弁8と、タービンバイパ
ス弁9と、復水器3と、復水系ポンプ4と、給水加熱器
7、復水給水ポンプ5、復水系逆止弁31とで形成される
環状の循環流路である。復水給水配管6の原子炉圧力容
器1入口部に設けた復水給水系止め弁32は閉止する。The pipe system to be cleaned by the method of the present invention is a main steam pipe final spool pipe 26 joined to the reactor pressure vessel 1,
Isolation valves 28 and 29 installed inside and outside the wall of the reactor containment vessel 27
, Main steam pipe 2, main steam stop valve 8, turbine bypass valve 9, condenser 3, condensate system pump 4, feed water heater 7, condensate feed water pump 5, condensate system check valve 31. It is an annular circulation flow path formed by. The condensate water supply system stop valve 32 provided at the inlet of the reactor pressure vessel 1 of the condensate water supply pipe 6 is closed.
なお、復水系逆止弁31の二次側以降、原子炉圧力容器ま
での配管系は予め工場にてフラッシング洗浄を実施し、
現場における洗浄液による洗浄対象から除外する。After the secondary side of the condensate system check valve 31, the piping system up to the reactor pressure vessel was previously flushed and cleaned at the factory,
Exclude from cleaning by the on-site cleaning liquid.
また、上記循環流路のうち、復水給水ポンプ5等の洗浄
が困難な機器には、仮設配管12でバイパスを形成する。In addition, a bypass is formed by the temporary pipe 12 for equipment such as the condensate water supply pump 5 that is difficult to clean among the circulation flow paths.
さらに、原子炉圧力容器1に主蒸気配管最終スプール配
管26および復水給水配管最終スプール配管33を予め溶接
接合した後に循環流路を形成するために、主蒸気配管2
の蒸気逃し安全弁の管台34と復水系逆止弁31のボンネッ
ト部とを仮設配管35で接続する。Further, in order to form the circulation flow path after the main steam pipe final spool pipe 26 and the condensate water supply pipe final spool pipe 33 are welded and joined to the reactor pressure vessel 1, the main steam pipe 2
The pipe base 34 of the steam relief safety valve and the bonnet part of the condensate system check valve 31 are connected by a temporary pipe 35.
また、原子炉圧力容器1に接合した主蒸気配管の開口部
を一対毎に原子炉容器内に配設した仮設配管36で相互連
通するように接続する。Further, the openings of the main steam pipes joined to the reactor pressure vessel 1 are connected to each other so as to communicate with each other by temporary pipes 36 arranged in the reactor vessel.
こうして、主蒸気系および復水給水系を環状に接続して
洗浄用の循環流路を形成した後、気密試験等を実施して
配管系に漏洩箇所がないことを確認して洗浄作業に移
る。In this way, after connecting the main steam system and the condensate water supply system in an annular shape to form a circulation flow path for cleaning, perform an airtight test etc. to confirm that there are no leak points in the piping system and proceed to cleaning work. .
洗浄作業の手順は、まず、第3図に示す洗浄装置30にて
調製された洗浄液を洗浄液ポンプ21にて移送し、出口逆
止弁16から循環流路内に注入し流路内に洗浄液を充満さ
せる。注入させた洗浄液は復水系ポンプ4によって循環
流路内を循環し、配管内面を洗浄する。所定の洗浄度が
得られるまで循環洗浄に使用された洗浄液は、排出用仮
設配管22を通って排出され、第4図に示す処理装置23に
て中和処理、沈澱処理された後に系外に排出される。The procedure of the cleaning work is as follows. First, the cleaning liquid prepared in the cleaning device 30 shown in FIG. 3 is transferred by the cleaning liquid pump 21, and is injected into the circulation flow path from the outlet check valve 16 to supply the cleaning liquid into the flow path. Fill up. The injected cleaning liquid is circulated in the circulation passage by the condensate system pump 4 to clean the inner surface of the pipe. The cleaning liquid used for circulation cleaning until a predetermined cleaning degree is discharged through the temporary discharge pipe 22 and neutralized and precipitated by the processing device 23 shown in FIG. Is discharged.
上記洗浄作業の完了後、洗浄液の循環流路を形成してい
たバイパス用仮設配管12、注水用仮設配管15、排出用仮
設配管22、原子炉圧力容器廻りの仮設配管35,36等の仮
設配管を撤去し、復水系逆止弁31のボンネットを取付け
る。そして、蒸気逃し安全弁の管台34盲板を取付けるこ
とによって復旧作業が完了し、直ちに原子炉圧力容器の
耐圧試験を実施することができる。After completion of the cleaning work, temporary pipes for bypass 12, which formed a circulation flow passage for the cleaning liquid, temporary pipe for water injection 15, temporary pipe for discharge 22, temporary pipes 35, 36 around the reactor pressure vessel, etc. And attach the bonnet of the condensate check valve 31. Then, the recovery work is completed by mounting the blind plate 34 of the steam relief valve, and the pressure resistance test of the reactor pressure vessel can be carried out immediately.
すなわち、本発明方法によれば、原子炉圧力容器の耐圧
試験時に必要とされる主蒸気系と復水給水系の最終スプ
ール配管が予め原子炉圧力容器に接合されており、その
状態で洗浄作業が実施される。そして、洗浄後の復旧作
業には最終スプール配管の組立および溶接が含まれず、
僅かな仮設配管の撤去作業のみで復旧作業が完了するた
め、その復旧作業まで含めた配管の洗浄工程が大幅に短
縮される。That is, according to the method of the present invention, the final spool pipes of the main steam system and the condensate water supply system, which are required during the pressure resistance test of the reactor pressure vessel, are joined to the reactor pressure vessel in advance, and the cleaning work is performed in that state. Is carried out. And the recovery work after cleaning does not include the assembly and welding of the final spool pipe,
Since the restoration work is completed with only a small amount of work for removing the temporary piping, the pipe cleaning process including the restoration work is greatly shortened.
また、原子炉圧力容器に接合した主蒸気配管の開口部を
一対毎に仮設配管で接続しているため、洗浄液が主蒸気
配管の最終スプール配管内にも流通する。したがって、
洗浄対象となる配管領域が従来方法と比較して拡大さ
れ、より清浄度の高い配管系とすることができる。Further, since the opening of the main steam pipe joined to the reactor pressure vessel is connected to each pair by a temporary pipe, the cleaning liquid also flows into the final spool pipe of the main steam pipe. Therefore,
The piping region to be cleaned is expanded as compared with the conventional method, and the piping system with higher cleanliness can be obtained.
本発明に係る原子炉系の配管洗浄方法によれば、最終ス
プール配管が予め原子炉圧力容器に接合されており、こ
の状態で洗浄作業が実施されるため、洗浄作業完了後の
復旧作業は仮設配管の撤去のみである。したがって、従
来方法のように仮設配管の撤去後に最終スプール配管の
組立溶接を行なう場合と比較して復旧作業工程が大幅に
簡素化され、原子力プラントの建設工期が大幅に短縮さ
れる。According to the reactor system pipe cleaning method of the present invention, since the final spool pipe is joined to the reactor pressure vessel in advance and the cleaning work is performed in this state, the recovery work after the cleaning work is temporarily performed. Only the removal of piping. Therefore, as compared with the case where the final spool pipe is assembled and welded after removing the temporary pipe as in the conventional method, the recovery work process is greatly simplified, and the construction period of the nuclear power plant is greatly shortened.
また、原子炉圧力容器に接合した主蒸気配管の開口部を
一対毎に仮設配管で接続しているため、洗浄液が主蒸気
配管の最終スプール配管内にも流れ、洗浄される配管区
域が拡大される。In addition, since the opening of the main steam pipe joined to the reactor pressure vessel is connected to each pair by temporary pipe, the cleaning liquid also flows into the final spool pipe of the main steam pipe, expanding the pipe area to be cleaned. It
第1図は本発明に係る配管洗浄方法を実施する場合の配
管系統例を示す系統図、第2図は従来の配管洗浄方法を
実施する場合の配管系統を示す系統図、第3図は洗浄装
置の構成を示す系統図、第4図は使用済洗浄水の処理装
置を示す系統図である。 1……原子炉圧力容器、2……主蒸気配管、3……復水
器、4……復水系ポンプ、5……復水給水ポンプ、6…
…復水給水配管、7……給水加熱器、8……主蒸気止め
弁、9……タービンバイパス弁、10……タービンバイパ
ス配管、12……バイパス用仮設配管、13……連通用仮設
配管、14……洗浄装置、15……注水用仮設配管、16……
出口逆止弁、17……薬剤溶解タンク、18……純水貯蔵タ
ンク、19……薬注ポンプ、20……ミキシングヒータ、21
……洗浄液ポンプ、22……排出用仮設配管、23……処理
装置、24……中和槽、25……沈澱槽、26……主蒸気配管
最終スプール配管、27……原子炉格納容器、28,29……
隔離弁、30……給水加熱器、31……復水系逆止弁、32…
…復水給水系止め弁、33……復水給水配管最終スプール
配管、34……蒸気逃し安全弁の管台、35,36……仮設配
管。FIG. 1 is a system diagram showing an example of a piping system for carrying out the pipe cleaning method according to the present invention, FIG. 2 is a system diagram showing a piping system for carrying out a conventional pipe cleaning method, and FIG. 3 is a cleaning system. FIG. 4 is a system diagram showing the configuration of the device, and FIG. 4 is a system diagram showing the treatment device of used cleaning water. 1 ... Reactor pressure vessel, 2 ... Main steam pipe, 3 ... Condenser, 4 ... Condensate system pump, 5 ... Condensate feed pump, 6 ...
… Condensed water supply piping, 7 …… Supply water heater, 8 …… Main steam stop valve, 9 …… Turbine bypass valve, 10 …… Turbine bypass piping, 12 …… Bypass temporary piping, 13 …… Communication temporary piping , 14 …… Cleaning device, 15 …… Temporary piping for water injection, 16 ……
Outlet check valve, 17 …… chemical dissolution tank, 18 …… pure water storage tank, 19 …… chemical injection pump, 20 …… mixing heater, 21
...... Cleaning liquid pump, 22 …… Temporary pipe for discharge, 23 …… Treatment device, 24 …… Neutralization tank, 25 …… Precipitation tank, 26 …… Main steam piping final spool piping, 27 …… Reactor containment vessel, 28,29 ……
Isolation valve, 30 ... Water heater, 31 ... Condensation system check valve, 32 ...
… Condensed water supply stop valve, 33 …… Condensed water supply piping Final spool piping, 34 …… Steam relief safety valve base, 35,36 …… Temporary piping.
Claims (1)
力容器と取り合う部分を構成する最終スプール配管を予
め原子炉圧力容器に接合する一方、原子炉圧力容器に接
合した主蒸気配管の開口部を原子炉圧力容器内に配設し
た仮設配管で相互に連通するように接続し、さらに主蒸
気配管の逃し安全弁管台と原子炉圧力容器入口部におけ
る復水給水配管の逆止弁とを仮設配管で接続することに
よって主蒸気配管および復水給水配管を環状に接続して
洗浄液の循環流路を形成した後に、洗浄液を前記循環流
路内に注入し、所定時間洗浄液を循環することを特徴と
する原子炉系の配管洗浄方法。1. A main steam pipe and a condensate water supply pipe are joined to a reactor pressure vessel in advance while connecting a final spool pipe constituting a portion where the main steam pipe and the condensate water supply pipe are joined to the reactor pressure vessel, and an opening of the main steam pipe joined to the reactor pressure vessel. Parts are connected so that they can communicate with each other through temporary piping installed in the reactor pressure vessel, and the relief safety valve base of the main steam piping and the check valve of the condensate water supply piping at the inlet of the reactor pressure vessel are connected. After connecting the main steam pipe and the condensate water supply pipe in an annular shape by connecting with a temporary pipe to form a circulation channel of the cleaning liquid, the cleaning liquid is injected into the circulation channel, and the cleaning liquid is circulated for a predetermined time. A characteristic method for cleaning the piping of a reactor system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61290351A JPH0679704B2 (en) | 1986-12-08 | 1986-12-08 | Reactor system piping cleaning method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61290351A JPH0679704B2 (en) | 1986-12-08 | 1986-12-08 | Reactor system piping cleaning method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63143990A JPS63143990A (en) | 1988-06-16 |
| JPH0679704B2 true JPH0679704B2 (en) | 1994-10-12 |
Family
ID=17754921
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61290351A Expired - Lifetime JPH0679704B2 (en) | 1986-12-08 | 1986-12-08 | Reactor system piping cleaning method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0679704B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4492880B2 (en) * | 2006-03-24 | 2010-06-30 | 株式会社神鋼環境ソリューション | Method for cleaning sodium-using facility and method for manufacturing sodium dispersion by performing cleaning and manufacturing sodium dispersion |
| CN102601085B (en) * | 2012-03-16 | 2014-06-18 | 中广核工程有限公司 | System and method for washing nuclear loop of nuclear island |
-
1986
- 1986-12-08 JP JP61290351A patent/JPH0679704B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS63143990A (en) | 1988-06-16 |
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