JPS61129598A - Method of inhibiting storage of radioactivity to nuclear reactor primary system - Google Patents

Method of inhibiting storage of radioactivity to nuclear reactor primary system

Info

Publication number
JPS61129598A
JPS61129598A JP59250880A JP25088084A JPS61129598A JP S61129598 A JPS61129598 A JP S61129598A JP 59250880 A JP59250880 A JP 59250880A JP 25088084 A JP25088084 A JP 25088084A JP S61129598 A JPS61129598 A JP S61129598A
Authority
JP
Japan
Prior art keywords
reactor
water
primary system
plant
radioactivity
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
Application number
JP59250880A
Other languages
Japanese (ja)
Inventor
実 小林
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.)
Toshiba Corp
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Atomic Industry Group Co 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 Toshiba Corp, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP59250880A priority Critical patent/JPS61129598A/en
Publication of JPS61129598A publication Critical patent/JPS61129598A/en
Pending 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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 [発明の技術分野] 本発明は沸騰水型原子力発電プラント(以下BWRプラ
ントと略す)における原子炉一次系機器・配管の内面に
酸化被膜を形成した原子炉一次系への放射能M積抑制方
法に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a reactor primary system in which an oxide film is formed on the inner surface of the reactor primary system equipment and piping in a boiling water nuclear power plant (hereinafter referred to as a BWR plant). The present invention relates to a radioactive M product suppression method.

し発明の技術的背景とその問題点] 一般に、8WRプラントでは、プラント出力運転に際し
高温水各件下になるため原子炉一次系に用いられている
機器・配管の内面に酸化被膜が形成される。この酸化被
膜が形成される際に、原子炉水中の放射性金属例えば、
コバルト−60,コバルト−58、マンガン−54など
が被膜の中に取り込まれ、原子炉一次系機器・配管の内
面の放射線m率を上昇する。
[Technical background of the invention and its problems] Generally, in an 8WR plant, an oxide film is formed on the inner surface of equipment and piping used in the reactor primary system because the plant is exposed to high temperature water during plant output operation. . When this oxide film is formed, radioactive metals in the reactor water, such as
Cobalt-60, cobalt-58, manganese-54, etc. are incorporated into the coating and increase the radiation m rate on the inner surface of the reactor primary system equipment and piping.

そのためプラント定検時に原子炉系機器・配管を点検す
る作業従事者の放射線被曝の増大につながることが知ら
れている。原子炉一次系機器・配管の放射線量率低減の
対象として原子炉水中の放射性金属濃度を減少すること
が試みられ、原子炉一次系機器・配管材料の耐食性向上
、コバルト含有量の低減化などが実プラントで実施され
ている。
This is known to lead to increased radiation exposure for workers who inspect reactor system equipment and piping during regular plant inspections. Efforts have been made to reduce the concentration of radioactive metals in reactor water as a target for reducing the radiation dose rate of primary reactor equipment and piping. It is being implemented in an actual plant.

しかしながら、これらの対策は、必ずしも十分満足でき
るまで機器・配管表面の放射線量率を低減できていない
However, these measures have not necessarily been able to sufficiently reduce the radiation dose rate on the surfaces of equipment and piping.

一方、機器・配管の放射線量率低減対策の他の方法とし
て、放射性金属物質が発生する前に機器・配管の内面に
予め、酸化被膜を形成し、プラント核加熱後に形成され
る機器・配管の内面の酸化被膜形成速度を減少し、この
酸化被膜に放射性金属物質をとり込む量を抑制する方法
が考えられる。
On the other hand, as another method to reduce the radiation dose rate of equipment and piping, an oxide film is formed on the inner surface of equipment and piping before radioactive metal substances are generated, and the One possible method is to reduce the rate of oxide film formation on the inner surface and to suppress the amount of radioactive metal substances incorporated into this oxide film.

しかしながら、この酸化被膜形成させる方法を実用化す
るために特にBWRプラント内で実施する場合、酸化処
理を施すための例えば熱源の確保および溶存酸素の供給
などが必要となるが、他系統の運転に依存せざるを得な
い状態が多い。そのため、BWRプラントの建設時およ
び試運粘時等における運用上の問題点として大きな困難
を伴なうことが想像される。
However, in order to put this method of forming an oxide film into practical use, especially in a BWR plant, it is necessary to secure a heat source and supply dissolved oxygen for the oxidation treatment, but it is difficult to operate other systems. There are many situations where we have no choice but to depend on them. Therefore, it can be imagined that major operational problems will arise during the construction and trial run of a BWR plant.

[発明の目的] 本発明は、この点にかんがみなされたもので、BWRプ
ラントの配管・機器の内面に放射性金属例えばコバルト
−60、コバルト−58、マンガン−54などが蓄積さ
れずかつ放射WAm率が上昇しないで、作業従事者の放
射線被曝を防止できる原子炉一次系への放射能蓄積抑制
方法を提供することにある。
[Objective of the Invention] The present invention was conceived in view of this point, and it is possible to prevent radioactive metals such as cobalt-60, cobalt-58, manganese-54, etc. from being accumulated on the inner surfaces of piping and equipment of a BWR plant, and to reduce the radiation WAm rate. An object of the present invention is to provide a method for suppressing the accumulation of radioactivity in the primary system of a nuclear reactor, which prevents workers from being exposed to radiation without increasing the amount of radioactivity.

i    「発明の概要] 本発明は、上記目的を達成するために、沸騰水型原子力
発電プラントにおけるプラント核加熱前に再循環系(P
LR)ポンプで原子炉水を連続再循環し、PLRポンプ
の運転時に発生するジュール熱で原子炉の核加熱前に原
子炉に張った原子炉水をBWRプラント通常運転条件温
度に維持し、かつ、同条件下の溶存酸素濃度に維持して
プラントの核加熱前に原子炉一次系機器・配管の内面に
予め、酸化被膜を形成し原子炉プラントの核加熱後に発
生する放射性金属物質の機器・配管表面への蓄積を抑制
した原子炉一次系への放射能蓄積抑制方法である。
i "Summary of the Invention" In order to achieve the above object, the present invention provides a recirculation system (P
(LR) pump continuously recirculates the reactor water, and the Joule heat generated during operation of the PLR pump maintains the reactor water filled in the reactor at the BWR plant normal operating temperature before the nuclear heating of the reactor, and By maintaining the dissolved oxygen concentration under the same conditions, an oxide film is formed on the inner surface of the reactor primary system equipment and piping before the nuclear heating of the plant, and radioactive metal materials generated after the nuclear heating of the reactor plant are removed. This is a method of suppressing the accumulation of radioactivity in the primary system of a nuclear reactor, which suppresses accumulation on the piping surface.

し発明の実施例] 以下、本発明の一実施例を図について説明する。Examples of the invention] Hereinafter, one embodiment of the present invention will be described with reference to the drawings.

図は、BWRプラントの基本システム図である。The figure is a basic system diagram of a BWR plant.

通常のプラント核加熱運転では、原子炉1内に配置され
た炉心2の核熱料により発生した蒸気は主蒸気ライン3
を通りタービン4を回転し、発電機5を駆動することに
より電気を供給する。タービン4で仕事をしたのちの蒸
気は主復水器6により復水となる。復水は復水浄化装置
7で浄化された後給水ヒータ8にて加熱され原子炉1に
戻るという循環システムになっている。
In normal plant nuclear heating operation, steam generated by the nuclear heating material in the core 2 located in the reactor 1 is transferred to the main steam line 3.
, which rotates the turbine 4 and drives the generator 5 to supply electricity. The steam after doing work in the turbine 4 becomes condensed water in the main condenser 6. The condensate is purified by a condensate purification device 7, heated by a feed water heater 8, and returned to the reactor 1, forming a circulation system.

本発明では、上記システムを用いるが、使用方法が通常
核加熱運転と全く異なる。それは、炉心2の核燃料を燃
や寸ことなく原子炉水を放射能を除く通常BWR運転条
件下にして運転することにある。すなわち、炉心2の核
燃料を利用しないでPLRポンプ9を運転することによ
り発生するジュール熱で水温をBWR通常運転条件下と
同等温度に上昇し、原子炉水サンプリングライン10を
用いて酸素を供給しBWR通常運転条件下と同等の原子
炉水溶存酸素濃度とした状態で運転をN続することにあ
る。
In the present invention, the above system is used, but the method of use is completely different from normal nuclear heating operation. The goal is to operate the reactor under normal BWR operating conditions, which remove radioactivity from the reactor water, without burning the nuclear fuel in the reactor core 2. That is, the Joule heat generated by operating the PLR pump 9 without using the nuclear fuel in the reactor core 2 raises the water temperature to the same temperature as under normal BWR operating conditions, and oxygen is supplied using the reactor water sampling line 10. The aim is to continue operation for N hours with the dissolved oxygen concentration in the reactor water being the same as under normal BWR operating conditions.

本発明は、例えば次のようにして行なう。The present invention is carried out, for example, as follows.

原子炉内い水を主蒸気ライン3のレベル以下まで張る。Fill the reactor with water to below the level of main steam line 3.

この時給水止め弁11は閉じておく。つぎに主蒸気隔離
弁12、タービンバイパス弁13を開は主蒸気止め14
を閉じて、真空ポンプ15を運転することにより原子炉
系及びタービン系を真空に維持する。ホットウェル16
には水を張り、復水ポンプ17を運転することにより復
水浄化装置7を通し、水を浄化しながらホットウェル1
6に水を戻す角循環運転を行なう。このホットウェル1
6にはタービングランドシール水が流入するため、その
余剰水は復水浄化装置7を通った侵、復水タンク18に
回収する。これにより、ボットウェル16を循環する水
は溶存酸素が低い状態に維持できる。
At this time, the water supply stop valve 11 is kept closed. Next, the main steam isolation valve 12 and the turbine bypass valve 13 are opened by the main steam stop 14.
The reactor system and turbine system are maintained in a vacuum by closing the reactor system and operating the vacuum pump 15. hot well 16
The hot well 1 is filled with water and passed through the condensate purification device 7 by operating the condensate pump 17, purifying the water.
Perform angular circulation operation to return water to step 6. This hot well 1
Since the turbine gland seal water flows into the turbine gland 6, the excess water passes through the condensate purification device 7 and is collected in the condensate tank 18. Thereby, the water circulating through the bot well 16 can be maintained in a state of low dissolved oxygen.

つづいて、原子炉水をPLRポンプ9を連続運転するこ
とにより発生するジュール熱により昇温し、原子炉水中
の溶存酸素を主蒸気ライン3を通して脱気し、溶存酸素
濃度をBWR通電運転条件下と同等またはそれ以下にす
る。その後主蒸気隔離弁12を閉じ、制御棒駆動ポンプ
19を運転し、制御棒駆e機構20より、脱気復水を原
子炉1が満杯になるまで注入する。原子炉へのこの注入
方法により原子炉水溶存酸素がBWR通常運転条件下の
溶存酸素レベルと同等もしくはそれ以下となっている。
Next, the reactor water is heated by Joule heat generated by continuous operation of the PLR pump 9, dissolved oxygen in the reactor water is degassed through the main steam line 3, and the dissolved oxygen concentration is adjusted under the BWR energized operating conditions. be equal to or less than. Thereafter, the main steam isolation valve 12 is closed, the control rod drive pump 19 is operated, and degassed condensate is injected from the control rod drive mechanism 20 until the reactor 1 is full. This method of injection into the reactor results in dissolved oxygen in the reactor water being equal to or lower than dissolved oxygen levels under normal BWR operating conditions.

仮りに溶存酸素がBWR通常運転条件下以下の場合には
、原子炉水サンプリングライン10から溶存酸素を注入
し、8WR通常運転条件下と同等の溶存酸素レベルに維
持する。原子炉水の浄化は、原子炉浄化系21により行
ない原子炉水質をBWR通常運転条件下と同様に維持す
る。
If the dissolved oxygen is below the BWR normal operating conditions, dissolved oxygen is injected from the reactor water sampling line 10 to maintain the dissolved oxygen level equivalent to the 8WR normal operating conditions. Purification of the reactor water is carried out by the reactor purification system 21, and the reactor water quality is maintained in the same manner as under normal BWR operating conditions.

これらの運転により、原子炉水中の溶存酸素、水質をB
WR通常運転条件下に維持コントロールした状態でPL
Rポンプ9を連続運転しポンプジュール熱により、BW
R通常運転条件下まで昇温する。
Through these operations, dissolved oxygen and water quality in the reactor water are reduced to B.
WR PL with maintenance control under normal operating conditions
BW is increased by continuous operation of R pump 9 and pump Joule heat.
R Increase the temperature to normal operating conditions.

水温のバランスは高温の原子炉水を原子炉浄化系21を
通して主復水量14にドレンし、その6920分を制御
棒駆動機構20から復水を注入することにより行なう。
The water temperature is balanced by draining high-temperature reactor water into the main condensate volume 14 through the reactor purification system 21 and injecting condensate from the control rod drive mechanism 20 for 6920 minutes.

こうして、PLRポンプ9の連続運転により発生するジ
ュール熱を利用して原子炉水質をBWR通常運転未件下
と同条件で維持コントロールできる。
In this way, the Joule heat generated by the continuous operation of the PLR pump 9 can be used to maintain and control the reactor water quality under the same conditions as under normal BWR operation.

この運転を約100時間以上継続することにより、プラ
ントの核加熱前に、すなわち放射性金属1    が存
在しない状態で原子炉一次系機器・配管22の面及び原
子炉の内面に酸化被膜を形成することができる。
By continuing this operation for about 100 hours or more, an oxide film is formed on the surfaces of the reactor primary system equipment and piping 22 and on the inner surface of the reactor before the nuclear heating of the plant occurs, that is, in the absence of radioactive metal 1. I can do it.

[発明の効果] 以上説明したように、この核加熱前に本発明方法で酸化
被膜を形成しておくことに゛よってプラントの核加熱以
降は、酸化被膜の形成が抑制されるため、酸化被膜形成
段階で原子炉一次系機器・配管22及び原子炉との表面
に蓄積していく放射能金属の量が同様に抑制される。そ
の結果、原子炉一次系機器・配管の内表面への放射線量
率上昇が抑制され、プラント作業従事者の放射線被曝低
減がはかれることになり、BWRプラント運転上きわめ
て有用な効果がある。
[Effects of the Invention] As explained above, by forming an oxide film by the method of the present invention before nuclear heating, the formation of an oxide film is suppressed after the nuclear heating of the plant. The amount of radioactive metal that accumulates on the surface of the reactor primary system equipment/piping 22 and the reactor during the formation stage is similarly suppressed. As a result, the increase in radiation dose rate to the inner surface of the reactor primary system equipment and piping is suppressed, and the radiation exposure of plant workers is reduced, which is an extremely useful effect on BWR plant operation.

【図面の簡単な説明】[Brief explanation of the drawing]

図は本発明に係る原子炉一次系への放射能蓄積抑制方法
の一実地例を説明するための系統図である。
The figure is a system diagram for explaining an example of the method for suppressing radioactivity accumulation in the primary system of a nuclear reactor according to the present invention.

Claims (1)

【特許請求の範囲】[Claims] (1)沸騰水型原子力発電プラントにおける原子炉水再
循環ポンプの運転時に発生するジュール熱を利用して原
子炉一次系機器・配管の内面に酸化被膜を形成すること
を特徴とする原子炉一次系への放射能蓄積抑制方法。
(1) A nuclear reactor primary system characterized by forming an oxide film on the inner surface of reactor primary system equipment and piping using Joule heat generated during operation of a reactor water recirculation pump in a boiling water nuclear power plant. Method for suppressing radioactivity accumulation in the system.
JP59250880A 1984-11-28 1984-11-28 Method of inhibiting storage of radioactivity to nuclear reactor primary system Pending JPS61129598A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59250880A JPS61129598A (en) 1984-11-28 1984-11-28 Method of inhibiting storage of radioactivity to nuclear reactor primary system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59250880A JPS61129598A (en) 1984-11-28 1984-11-28 Method of inhibiting storage of radioactivity to nuclear reactor primary system

Publications (1)

Publication Number Publication Date
JPS61129598A true JPS61129598A (en) 1986-06-17

Family

ID=17214385

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59250880A Pending JPS61129598A (en) 1984-11-28 1984-11-28 Method of inhibiting storage of radioactivity to nuclear reactor primary system

Country Status (1)

Country Link
JP (1) JPS61129598A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103299199A (en) * 2011-01-17 2013-09-11 株式会社东芝 Transient recovery voltage measuring device, transient recovery voltage measuring method, and transient recovery voltage measuring program

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59143996A (en) * 1983-02-07 1984-08-17 株式会社日立製作所 Method of operating early oxydation of atomic power plant

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59143996A (en) * 1983-02-07 1984-08-17 株式会社日立製作所 Method of operating early oxydation of atomic power plant

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103299199A (en) * 2011-01-17 2013-09-11 株式会社东芝 Transient recovery voltage measuring device, transient recovery voltage measuring method, and transient recovery voltage measuring program

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