JPH01185492A - Feed water tubing circulating facility in nuclear power plant - Google Patents
Feed water tubing circulating facility in nuclear power plantInfo
- Publication number
- JPH01185492A JPH01185492A JP63008336A JP833688A JPH01185492A JP H01185492 A JPH01185492 A JP H01185492A JP 63008336 A JP63008336 A JP 63008336A JP 833688 A JP833688 A JP 833688A JP H01185492 A JPH01185492 A JP H01185492A
- Authority
- JP
- Japan
- Prior art keywords
- piping
- reactor
- condensate
- final stage
- feedwater
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 73
- 230000007797 corrosion Effects 0.000 claims abstract description 25
- 238000005260 corrosion Methods 0.000 claims abstract description 25
- 239000002826 coolant Substances 0.000 claims abstract description 19
- 238000000746 purification Methods 0.000 claims description 20
- 239000012535 impurity Substances 0.000 claims description 16
- 238000002955 isolation Methods 0.000 claims description 11
- 238000000926 separation method Methods 0.000 abstract 3
- 230000000694 effects Effects 0.000 description 3
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 230000004913 activation Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 230000008676 import Effects 0.000 description 1
- 230000002401 inhibitory effect Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
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
Landscapes
- Separation Using Semi-Permeable Membranes (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、原子力発電プラントの停止中における給水配
管の腐食抑制のために原子炉冷却材浄化系循環水により
給水配管内を循環できる設備を備えた原子力発電プラン
トにおける給水配管循環設備に関するものである。[Detailed Description of the Invention] [Field of Industrial Application] The present invention provides equipment that can circulate water within the water supply piping using circulating water from the reactor coolant purification system in order to suppress corrosion of the water supply piping during shutdown of a nuclear power plant. This relates to water supply piping circulation equipment in nuclear power plants equipped with
従来の原子力発電プラントは、例えば特開昭55−16
4081号公報に記載されているものがある。このプラ
ントの停止時は、第2図に示す様に給・復水系18は、
原子炉圧力容器外側隔離弁16を閉にし、給・復水再循
環系17の給・復水再循環弁23を開にする。給水ポン
プ22をバイパスし、復水ポンプ20により、復水脱塩
装置21.給水加熱器23を介して復水器19へもどる
循環保管を行う。しかし、最終段の給水加熱器以降の給
水配管4に関しては、原子炉建屋とタービン建屋間を継
ぐ連絡配管であり、本配管を含め循環運転をする場合は
、建屋間を大口径配管が往復する必要があるという問題
があった。しかし、本配管の腐食による原子炉への不純
物の持込み量及び、−次系配管の線量率上昇寄与が、他
の系統からの寄与に比べ十分低いものとの判断から、特
に配慮がされていなかった。しかし、近年の原子力発電
プラントは、−次系配管材料の改善、被ばく低減技術の
確立等により、プラン1〜全体の線量率が低下してきて
いることから、給水配管からの寄与が、無視できなくな
ってきている。Conventional nuclear power plants, for example,
There is one described in the 4081 publication. When the plant is stopped, the supply/condensate system 18 is operated as shown in Fig. 2.
The reactor pressure vessel outer isolation valve 16 is closed, and the feed/condensate recirculation valve 23 of the feed/condensate recirculation system 17 is opened. By bypassing the water supply pump 22, the condensate pump 20 operates the condensate desalination device 21. Circulating storage is performed in which the water returns to the condenser 19 via the feed water heater 23. However, the water supply piping 4 after the final stage feed water heater is a connecting piping that connects the reactor building and the turbine building, and when performing circulation operation including this piping, large-diameter piping must reciprocate between the buildings. The problem was that it was necessary. However, no particular consideration was given to the amount of impurities brought into the reactor due to corrosion of this piping and the contribution of secondary system piping to the increase in the dose rate, as it was judged to be sufficiently low compared to the contribution from other systems. Ta. However, in recent years in nuclear power plants, the overall dose rate from Plan 1 has been decreasing due to improvements in sub-system piping materials and the establishment of radiation exposure reduction technology, so the contribution from water supply piping can no longer be ignored. It's coming.
上記従来の原子力発電プラントにおいては、プラント停
止時は、復水器から最終段の給水加熱器までの配管は、
給・復水循環配管により循環保管をするか、あるいは系
統の水抜きを行ない給・復水系配管の腐食抑制を行なっ
ている。しかし、最終段の給水加熱器以降の配管につい
ては、循環配管がなく循環保管が出来ない。またドレン
ラインがないため水抜き乾燥保管も出来ず、配管内が溜
り水となり腐食が進行する。そのため、原子力発電プラ
ント起動時に停止中に発生した錆が原子炉内に持込まれ
放射化されるため、−次系配管の線量率を上昇させる問
題があった。In the above conventional nuclear power plant, when the plant is stopped, the piping from the condenser to the final stage feedwater heater is
Corrosion of the supply and condensate system piping is suppressed by storing the water in circulation using supply and condensate circulation piping, or by draining water from the system. However, the piping after the final stage feed water heater does not have circulation piping and cannot be stored in circulation. Also, since there is no drain line, water cannot be drained and stored dry, and water accumulates inside the pipes, causing corrosion. Therefore, rust generated during shutdown at the time of startup of a nuclear power plant is carried into the reactor and becomes radioactive, which poses a problem of increasing the dose rate of secondary system piping.
本発明の目的は、原子力発電プラントの停止時に、最終
段の給水加熱器上流側の配管同様、最終段の給水加熱器
以降の配管についても、循環保管あるいは、水抜き乾燥
保管が出来る給水配管循環設備を設けることにより、原
子力発電プラント停止時の給水配管の腐食抑制を行ない
、原子力発電プラント起動時に持込まれる錆を減少し得
るプラントを提供することにある。The purpose of the present invention is to provide a water supply piping circulation system that allows for circulation storage or drained dry storage of piping after the final stage feed water heater, as well as piping upstream of the final stage feed water heater, when a nuclear power plant is shut down. An object of the present invention is to provide a plant that can suppress corrosion of water supply piping when a nuclear power plant is shut down and reduce rust brought in when the nuclear power plant is started up by providing equipment.
上記目的は、(a)原子炉、(b)タービン、(C)発
電機、(d)復水器、復水中の不純物を除去する復水浄
化装置、給水を加熱する給水加熱器及び原子炉停止中に
給・復水系の腐食抑制のために設けられた給・復水再循
環配管とを有する給・復水系及び(e)原子炉、炉水中
の不純物を除去する原子炉浄化装置を含む原子炉冷却材
浄化系とを主たる構成要素とする原子力発電プラントに
おいて、最終段の給水加熱器下流側配管と前記原子炉冷
却材浄化装置下流側配管とを結ぶバイパス配管を設け、
かつ前記バイパス配管の最終段給水加熱器側接続部と該
最終段給水加熱器との間に隔離弁を設けることにより達
成される。The above purposes are (a) nuclear reactor, (b) turbine, (C) generator, (d) condenser, condensate purification device to remove impurities in condensate, feed water heater to heat feed water, and nuclear reactor. A feed/condensate system with feed/condensate recirculation piping installed to suppress corrosion of the feed/condensate system during shutdown, and (e) reactor, including a reactor purification system to remove impurities in reactor water. In a nuclear power plant whose main component is a reactor coolant purification system, a bypass piping is provided that connects the final stage feed water heater downstream piping and the reactor coolant purification device downstream piping,
This is achieved by providing an isolation valve between the final stage feed water heater side connection portion of the bypass piping and the final stage feed water heater.
本発明はプラント停止時の給水配管内の腐食を抑制する
ために、給水配管内を原子炉冷却材浄化系循環水により
循環する配管を備えたものであると共に、長期間原子力
発電プラントが停止する場合には、循環後2の配管によ
り給水配管内の水抜きができ、給水配管の乾燥保管を可
能にするものである。In order to suppress corrosion in the water supply piping when the plant is shut down, the present invention is equipped with piping in which circulating water from the reactor coolant purification system is circulated through the water supply piping. In such cases, the water in the water supply pipe can be drained by the second pipe after circulation, and the water supply pipe can be stored dry.
次に、原子力発電プラントにおける配管内環境の違いに
よる腐食量変化を第3図に示す、第3図のAは配管内を
満水状態で保管した場合の腐食量、Bは、配管内を水抜
き乾燥保管した場合の腐食量、Cは、配管内を@環体管
した場合の腐食量を示す。Next, Figure 3 shows changes in the amount of corrosion due to differences in the environment inside the piping in a nuclear power plant. The amount of corrosion when stored dry, C indicates the amount of corrosion when the inside of the pipe is @ring pipe.
Aの状態では、時間の経過とともに腐食が急激に進行す
る。一方、本発明により循環保管を実施すればCに示す
様に、はとんど腐食は進行しない。In state A, corrosion progresses rapidly over time. On the other hand, if circulation storage is carried out according to the present invention, corrosion will hardly progress as shown in C.
また、水抜き乾燥保管実施によっても、Bに示す様にC
の満水状態と比べ、十分に腐食抑制効果がある。Also, by draining water and storing it dry, C
It has a sufficient corrosion inhibiting effect compared to the full water condition.
実施例1
第1図に示す様に、最終段の給水加熱器下流側に給・復
水再循環系統から、給水配管4を隔離するため隔離弁9
を設置し、原子炉冷却材浄化系3と給水配管4を継ぐバ
イパス配管5で構成される。Embodiment 1 As shown in FIG. 1, an isolation valve 9 is installed downstream of the final stage feed water heater to isolate the feed water pipe 4 from the feed/condensate recirculation system.
The reactor coolant purification system 3 and the water supply pipe 4 are connected to each other by a bypass pipe 5.
最終段の給水加熱器以降の給水配管4は、最終段給水加
熱器下流隔離弁9、原子炉冷却材浄化系系統隔離弁15
を閉とし、バイパス配管入口弁6゜バイパス配管出口弁
7及び、原子炉圧力容器外側隔離弁16を開とすること
によって、原子炉冷却材浄化系ポンプ11により、原子
炉冷却材浄化系循環水が、バイパス配管5を通り、給水
配管4を通って@環することが可能となる。本実施例に
よれば、給水配管4内が循環保管され、原子力発電プラ
ント停止時の給水配管4からの腐食抑制が可能となる。The water supply piping 4 after the final stage feed water heater includes a final stage feed water heater downstream isolation valve 9 and a reactor coolant purification system isolation valve 15.
By closing the bypass piping inlet valve 6, bypass piping outlet valve 7, and opening the reactor pressure vessel outer isolation valve 16, the reactor coolant purification system pump 11 drains the reactor coolant purification system circulating water. However, it becomes possible to circulate through the bypass pipe 5 and the water supply pipe 4. According to this embodiment, the inside of the water supply pipe 4 is circulated and stored, making it possible to suppress corrosion from the water supply pipe 4 when the nuclear power plant is shut down.
これにより、原子力発電プラント起動時に原子炉への不
純物持込み量を抑制し、不純物が原子炉内で放射化され
一次系配管に付着することによる、−次系配管の線量率
上昇を抑制することが可能となる。As a result, it is possible to suppress the amount of impurities brought into the reactor at the time of startup of a nuclear power plant, and to suppress the increase in the dose rate of the secondary system piping due to impurities being activated in the reactor and adhering to the primary system piping. It becomes possible.
実施例2
本例は、原子力発電プラントの長期停止時に実施例1の
循環保管の後に、最終段の給水加熱器以降の給水配管4
の乾燥保管が下記により可能となる。実施例1のバイパ
ス配管5に系統水抜き用のバイパス配管ドレン弁8を設
け、さらに給水配管4に給水配管ベント弁を設けたもの
である。給水配管4の水抜きは、原子炉圧力容器外側隔
離弁16、最終段給水加熱器下流隔離弁9及び、バイパ
ス配管入口弁6を閉とし、バイパス配管ドレン弁8、バ
イパスライン出口弁7及び、給水配管ベント弁10を開
にすることにより可能となる。本実施例によれば、給水
配管4は、水抜き乾燥保管されることにより、実施例1
と同様、原子炉発電プラント起動時に原子炉への不純物
持込み量を抑制し、不純物が原子炉内で放射化され、−
次系配管に付着することによる、−次系配管の線量率上
昇を抑制することが可能となる。Example 2 In this example, after the circulation storage of Example 1 during a long-term shutdown of a nuclear power plant, the water supply piping 4 after the final stage feed water heater is
The dry storage of can be made possible by the following. The bypass pipe 5 of the first embodiment is provided with a bypass pipe drain valve 8 for draining system water, and the water supply pipe 4 is further provided with a water supply pipe vent valve. To drain water from the water supply pipe 4, close the reactor pressure vessel outer isolation valve 16, the final stage feed water heater downstream isolation valve 9, and the bypass pipe inlet valve 6, and close the bypass pipe drain valve 8, bypass line outlet valve 7, and This is possible by opening the water supply pipe vent valve 10. According to this embodiment, the water supply pipe 4 is drained and stored in a dry manner.
Similarly, when starting up a nuclear power plant, the amount of impurities brought into the reactor is suppressed, and the impurities are activated within the reactor and -
It becomes possible to suppress an increase in the dose rate of the secondary system piping due to adhesion to the secondary system piping.
本発明によれば、原子力発電プラント停止時に給水配管
から発生する錆を抑制し、原子力発電プラント起動時に
、原子炉への不純物の持込みを抑制することができる。According to the present invention, it is possible to suppress rust generated from water supply piping when a nuclear power plant is shut down, and to suppress import of impurities into the reactor when the nuclear power plant is started.
これにより、原子炉内での不純物の放射化による一次系
配管のa量率低減の効果がある。例えば、3ケ月のプラ
ント停止中に給水配管を従来通り満水保管した場合は、
約8kgの腐食が発生する。これを本発明により循環保
管した場合は、約0.1kgLか腐食しない。また、水
抜き保管した場合においても、0 、6 kgと従来と
比べ、十分少ない腐食量となる。This has the effect of reducing the a content ratio of the primary system piping due to activation of impurities within the reactor. For example, if the water supply piping is kept full of water as usual during a three-month plant shutdown,
Approximately 8 kg of corrosion occurs. When this is stored in circulation according to the present invention, about 0.1 kgL does not corrode. Furthermore, even when stored without water, the amount of corrosion is 0.6 kg, which is sufficiently small compared to conventional products.
給水配管からの腐食量が、給水に持込まれる不純物量の
約3分の1に相当することから、本発明により最終段の
給水加熱器以降の配管からの腐食量を低減すれば、原子
炉への不純物持込み量を3分の2に低減することができ
る。Since the amount of corrosion from the feedwater piping is equivalent to about one-third of the amount of impurities brought into the feedwater, if the amount of corrosion from the piping after the final stage feedwater heater is reduced by this invention, it will be possible to reduce the amount of corrosion to the reactor. The amount of impurities brought in can be reduced to two-thirds.
また、−次系配管の線量率が、原子炉へ持込まれる不純
物量に比例すると考えると、本発明により最終段の給水
加熱器以降の配管からの腐食量を低減すれば、−次系配
管のa量率も約3分の2に低減できる。Furthermore, considering that the dose rate of the secondary system piping is proportional to the amount of impurities brought into the reactor, if the amount of corrosion from the piping after the final stage feedwater heater is reduced by the present invention, the radiation dose rate of the secondary system piping will be reduced. The a content rate can also be reduced to about two-thirds.
第1図は本発明の原子力発電プラントの概略図、第2図
は従来のプラントの概略図、第3図は各種条件での腐食
量の変化を示すグラフである。
1・・・原子炉、3・・・原子炉冷却材浄化系配管、5
・・・バイパス配管、6・・・バイパス配管の入口弁、
7・・・バイパス配管の出口弁、8・・・バイパス配管
のドレン弁、9・・・最終段給水加熱器下流隔離弁、1
3・・・原子炉冷却材浄化系ろ過説塩装置、19・・・
復水器、24・・・給水加熱器。
条1 口
牛3m
吟n(につFIG. 1 is a schematic diagram of a nuclear power plant according to the present invention, FIG. 2 is a schematic diagram of a conventional plant, and FIG. 3 is a graph showing changes in the amount of corrosion under various conditions. 1... Nuclear reactor, 3... Reactor coolant purification system piping, 5
...Bypass piping, 6...Inlet valve of bypass piping,
7... Outlet valve of bypass piping, 8... Drain valve of bypass piping, 9... Final stage feed water heater downstream isolation valve, 1
3... Reactor coolant purification system filtration salt theory device, 19...
Condenser, 24... Feed water heater. Article 1 Kuchigyu 3m Gin (Nitsu)
Claims (1)
d)復水器、復水中の不純物を除去する復水浄化装置、
給水を加熱する給水加熱器及び原子炉停止中に給・復水
系の腐食抑制のために設けられた給・復水再循環配管と
を有する給・復水系及び(e)原子炉、炉水中の不純物
を除去する原子炉浄化装置を含む原子炉冷却材浄化系と
を主たる構成要素とする原子力発電プラントにおいて、
最終段の給水加熱器下流側配管と前記原子炉冷却材浄化
装置下流側配管とを結ぶバイパス配管を設け、かつ前記
バイパス配管の最終段給水加熱器側接続部と該最終段給
水加熱器との間に隔離弁を設けたことを特徴とする原子
力発電プラントにおける給水配管循環設備。 2、(a)原子炉、(b)タービン、(c)発電機、(
d)復水器、復水中の不純物を除去する復水浄化装置。 給水を加熱する給水加熱器及び原子炉停止中に給・復水
系の腐食抑制のために設けられた給・復水再循環配管と
を有する給・復水系及び(e)原子炉、炉水中の不純物
を除去する原子炉浄化装置を含む原子炉冷却材浄化系と
を主たる構成要素とする原子力発電プラントにおいて、
最終段の給水加熱器下流側配管と前記原子炉冷却材浄化
装置下流側配管とを結ぶバイパス配管を設け、かつ前記
バイパス配管の最終段給水加熱器側接続部と該最終段給
水加熱器との間に隔離弁を設けると共に、前記バイパス
配管の一部に水抜き配管を設けたことを特徴とする原子
力発電プラントにおける給水配管循環設備。[Claims] 1. (a) nuclear reactor, (b) turbine, (c) generator, (
d) condenser, condensate purification device for removing impurities in condensate;
A feedwater/condensate system that has a feedwater heater that heats the feedwater and feed/condensate recirculation piping installed to suppress corrosion of the feedwater/condensate system during reactor shutdown, and (e) reactor and reactor water. In a nuclear power plant whose main component is a reactor coolant purification system including a reactor purification device that removes impurities,
A bypass piping is provided that connects the downstream piping of the final stage feedwater heater and the downstream piping of the reactor coolant purification device, and a connecting portion of the bypass piping on the final stage feedwater heater side and the final stage feedwater heater are provided. Water supply piping circulation equipment in a nuclear power plant, characterized by having an isolation valve installed between them. 2, (a) nuclear reactor, (b) turbine, (c) generator, (
d) Condenser, a condensate purification device that removes impurities in condensate. A feedwater/condensate system that has a feedwater heater that heats the feedwater and feed/condensate recirculation piping installed to suppress corrosion of the feedwater/condensate system during reactor shutdown, and (e) reactor and reactor water. In a nuclear power plant whose main component is a reactor coolant purification system including a reactor purification device that removes impurities,
A bypass piping is provided that connects the downstream piping of the final stage feedwater heater and the downstream piping of the reactor coolant purification device, and a connecting portion of the bypass piping on the final stage feedwater heater side and the final stage feedwater heater are provided. A water supply piping circulation system in a nuclear power plant, characterized in that an isolation valve is provided between the bypass piping and a water drain piping is provided in a part of the bypass piping.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63008336A JPH01185492A (en) | 1988-01-20 | 1988-01-20 | Feed water tubing circulating facility in nuclear power plant |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63008336A JPH01185492A (en) | 1988-01-20 | 1988-01-20 | Feed water tubing circulating facility in nuclear power plant |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH01185492A true JPH01185492A (en) | 1989-07-25 |
Family
ID=11690352
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP63008336A Pending JPH01185492A (en) | 1988-01-20 | 1988-01-20 | Feed water tubing circulating facility in nuclear power plant |
Country Status (1)
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JP (1) | JPH01185492A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US10678538B2 (en) | 2013-06-19 | 2020-06-09 | International Business Machines Corporation | Generating an operating procedure manual |
US10922107B2 (en) | 2014-09-16 | 2021-02-16 | International Business Machines Corporation | Apparatus and method for realizing runtime system for programming language |
-
1988
- 1988-01-20 JP JP63008336A patent/JPH01185492A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US10678538B2 (en) | 2013-06-19 | 2020-06-09 | International Business Machines Corporation | Generating an operating procedure manual |
US10922107B2 (en) | 2014-09-16 | 2021-02-16 | International Business Machines Corporation | Apparatus and method for realizing runtime system for programming language |
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