JPS60256100A - Method of decontaminating nuclear reactor system piping - Google Patents

Method of decontaminating nuclear reactor system piping

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Publication number
JPS60256100A
JPS60256100A JP59110910A JP11091084A JPS60256100A JP S60256100 A JPS60256100 A JP S60256100A JP 59110910 A JP59110910 A JP 59110910A JP 11091084 A JP11091084 A JP 11091084A JP S60256100 A JPS60256100 A JP S60256100A
Authority
JP
Japan
Prior art keywords
reactor
reactor system
gas
decontamination
system 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.)
Pending
Application number
JP59110910A
Other languages
Japanese (ja)
Inventor
柳沢 幸
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
Original Assignee
Toshiba Corp
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 filed Critical Toshiba Corp
Priority to JP59110910A priority Critical patent/JPS60256100A/en
Publication of JPS60256100A publication Critical patent/JPS60256100A/en
Pending legal-status Critical Current

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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所(以下BWRと略す)に
おける原子炉系配管の除染方法に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a method for decontaminating nuclear reactor system piping in a boiling water nuclear power plant (hereinafter abbreviated as BWR).

[発明の技術向背m] 通常、BWRプラントにおいては一次冷却水として純水
を用い原子炉圧力器にて蒸気を発生さぜCいる。この原
子炉圧力容器内で(,1炉水中の金属不純物が中性子照
射により放射化され放射性金属イオン″C02+、54
 M 01+等が生成される。この放射性金属イオンは
原子炉圧力容器に接続して設置されCいる原子炉水再循
環ライン内を流動づる。
[Technical Background of the Invention] Normally, in a BWR plant, pure water is used as primary cooling water and steam is generated in a reactor pressure vessel. In this reactor pressure vessel (1) Metal impurities in the reactor water are activated by neutron irradiation and radioactive metal ions "C02+, 54
M 01+ etc. are generated. The radioactive metal ions flow through a reactor water recirculation line connected to the reactor pressure vessel.

このため原子炉再循環ライン内表面にはC02+、’M
n ’+等の放射能が付着する。
Therefore, the inner surface of the reactor recirculation line has C02+, 'M
Radioactivity such as n'+ is attached.

BWRプラントは添附図に示したような原子炉系を有し
ている。
The BWR plant has a nuclear reactor system as shown in the attached diagram.

すなわち、原子炉圧力容器1内には中火部に炉心2が配
置され、この炉心2の側面にジェットポンプ3が配設さ
れている。また炉心2の上)5には気液分離器4および
蒸気乾燥器5が設(プられている。炉心2で加熱された
蒸気は気液分前器4および蒸気乾燥器5を通過し、主蒸
気ライン6から図示してないタービン系へ送られる。タ
ービン系から復水器を経て戻される復水は浄化されて再
び給水ライン7から原子炉圧力容器1内へ供給される。
That is, a reactor core 2 is disposed in a medium heat section within a reactor pressure vessel 1, and a jet pump 3 is disposed on a side surface of this reactor core 2. A gas-liquid separator 4 and a steam dryer 5 are installed above the core 2. The steam heated in the core 2 passes through a gas-liquid divider 4 and a steam dryer 5. It is sent from the main steam line 6 to a turbine system (not shown).Condensate returned from the turbine system via a condenser is purified and then supplied to the reactor pressure vessel 1 from the water supply line 7 again.

ところで前記ジェットポンプ3から流用される水は再循
環ポンプ9、バルブ10から原子炉再循環フィン8を通
って再びジェットポンプ3へ流入する。この再循環フィ
ン8は原子炉水を1!1¥−するためのもので゛あり、
曲りくねった配管構造になっている。
By the way, the water diverted from the jet pump 3 flows from the recirculation pump 9 and the valve 10 through the reactor recirculation fins 8 and into the jet pump 3 again. This recirculation fin 8 is for recirculating the reactor water.
It has a winding piping structure.

なお、図中符号11は原子炉D:力調整用気体ライン、
12は同しく気体ライン11のポンプ、13は気体圧力
調節かをそれぞれ示している。
In addition, the reference numeral 11 in the figure is reactor D: gas line for force adjustment;
12 also indicates a pump for the gas line 11, and 13 indicates a gas pressure regulator.

[背景技術の問題点1 しかして上記原子炉系における原子炉再循環ライン8の
配管内面の放射能を除去する方法が見出されていなかっ
たが、最近になって種々の化学薬品を用いた化学的除染
方法が開発される様になってきた。この除染方法は弱酸
、弱酸塩、またはキレート剤等の化学薬品を用い、配管
の内面の酸化皮膜内に取り込まれた放射性金属イオン(
例えば錦C62+、!″Mrl”等)を酸化皮膜ごと溶
解させ除染する方法eある。
[Problem in the Background Art 1 However, no method has been found for removing radioactivity from the inner surface of the reactor recirculation line 8 in the above-mentioned nuclear reactor system, but recently, methods using various chemicals have been developed. Chemical decontamination methods are beginning to be developed. This decontamination method uses chemicals such as weak acids, weak salt salts, or chelating agents, and uses radioactive metal ions (
For example, Nishiki C62+! There is a method of decontaminating the oxide film (e.g. "Mrl") by dissolving it together with the oxide film.

しかしながら、この方法は原子炉系配管の構造上からそ
の配管内に満たした除染液を流動さけることができなか
った。このため配管のすき間部や滞溜部におい(+、L
敢射能が11着した酸化皮膜の溶解が効率良く行なわれ
ていないでいた。したがって被除染物である原子炉系配
管内面の除染が均一に行なわれない状態どなっていた。
However, in this method, due to the structure of the reactor system piping, it was not possible to prevent the decontamination liquid from flowing inside the piping. For this reason, odors (+, L
The oxide film with 11 particles was not dissolved efficiently. Therefore, the inner surface of the reactor system piping, which is the object to be decontaminated, was not uniformly decontaminated.

また溶解していない酸化皮膜を溶解しようとしC除染の
実7Il!時間を長くすると既に酸化皮膜が溶解してい
る部分Cは配管地金そのbのが侵されてしまうという問
題点が生じ−Cいた。
In addition, an attempt is made to dissolve the undissolved oxide film, and C decontamination fruit 7Il! If the time is increased, a problem arises in that the piping base metal (B) is attacked in the portion (C) where the oxide film has already been dissolved.

[発明の目的コ 本発明は上記問題点を解決するためになされたもので、
BWRプラン]への原子炉系の化学的除染方法においで
効率の良い、しかも均一に除染づることができる原子炉
系ISi!管の除染方法を提供することにある。
[Object of the Invention] The present invention has been made to solve the above problems,
BWR Plan] Reactor system ISi is an efficient chemical decontamination method for the reactor system that can be uniformly decontaminated! The object of the present invention is to provide a method for decontaminating pipes.

[発明の概要] 本発明は沸騰水型原子力′R電所の原子炉系配管の内面
を化学的に除染する方法にイ5いて、前記原子炉系配管
内に化学除染液を流入するとともに該化学除染液内に気
泡を吹き込むことを特徴どする原子炉系配管の除染方法
である。
[Summary of the Invention] The present invention provides a method for chemically decontaminating the inner surface of the reactor system piping of a boiling water nuclear power station, including flowing a chemical decontamination liquid into the reactor system piping. This is a method for decontaminating nuclear reactor piping, which is characterized by blowing air bubbles into the chemical decontamination liquid.

[発明の実施例) 本発明の〜実施例について前記添II1図により説明づ
る。添附図において前述したように原子炉圧力容器1の
下部には原子炉1り循環ライン8の入口8aおよび出口
8bが設けられている。原子炉水はこのライン8および
ジェットポンプ3を通じて循環攪拌され(いる。そして
原子炉再結1j%ライン8の配管内面の除染を行なうに
は次のように再循環ライン8に除染液および気体の供給
ラインを設ける。刀なわら、再循環ライン8にバイパス
ライン14を設け、このバイパスライン14に切換えバ
ルブ15を介在させる。そして、バイパスライン14に
除染液注入外16およびガス吹込口17を取着する。除
染液注入外16には除染液タンク18から除染液供給ポ
ンプ21、バルブ25を有する除染液供給ライン22が
接続される。また、ガス吹込口17には気体ボンベ19
からバルブ24を有する気体供給ライン20が接続され
る。
[Embodiments of the Invention] Examples of the present invention will be explained with reference to Figure II1 above. As described above in the accompanying drawings, the lower part of the reactor pressure vessel 1 is provided with an inlet 8a and an outlet 8b of the reactor circulation line 8. The reactor water is circulated and agitated through this line 8 and the jet pump 3.In order to decontaminate the inner surface of the reactor reconsolidation line 8, decontamination liquid and water are added to the recirculation line 8 as follows. A gas supply line is provided.In addition, a bypass line 14 is provided in the recirculation line 8, and a switching valve 15 is interposed in this bypass line 14.A decontamination liquid injection port 16 and a gas inlet are provided in the bypass line 14. A decontamination liquid supply line 22 having a decontamination liquid supply pump 21 and a valve 25 is connected from the decontamination liquid tank 18 to the decontamination liquid injection port 16. gas cylinder 19
A gas supply line 20 having a valve 24 is connected thereto.

しかして、除染液を除染液タンク18から除染液タンク
16を通して再循環ライン8内に満す。
Thus, the recirculation line 8 is filled with decontamination liquid from the decontamination liquid tank 18 through the decontamination liquid tank 16 .

次に気体ボンベ19内の気体をガス吹さ込み口17がら
再結1■ライン8内にガス吹き込む。この気体は配管の
酸化皮膜の状態にJ、す仝気、窒素、酸素、水素または
アルゴンから選らばれた少なくとも一種の気体を用いる
。ガス吹き込み口17には気体を気泡状とする効果の大
きい焼結金属を使用でることが望ましい。ガス吹き込み
口17は原子炉再循環ライン8内全体に気泡が流れる様
に複数の箇所に設置づることが望ましい。この様に除染
液内に気泡を送り込むことにより、除染液に運動を生じ
させることができ攪拌効果が旧1−る。また気泡そのも
のによる洗浄効果も加わり従来方法より大幅に除染効果
が良くなる。また除染液に流動が生じるのぐ、配管の内
面が均一に除染され、その結果として配管地金が侵され
る口ともなくなり、材料劣化が防止できる。
Next, the gas in the gas cylinder 19 is blown into the recombination line 8 through the gas inlet 17. At least one gas selected from nitrogen, oxygen, hydrogen, or argon is used as this gas to maintain the state of the oxide film on the piping. It is desirable to use sintered metal for the gas inlet 17, which has a great effect of making gas bubbles. It is desirable that the gas inlet 17 be installed at a plurality of locations so that air bubbles flow throughout the reactor recirculation line 8. By introducing air bubbles into the decontamination liquid in this manner, it is possible to cause the decontamination liquid to move, thereby increasing the stirring effect. In addition, the cleaning effect of the bubbles themselves is added, and the decontamination effect is significantly better than that of conventional methods. Further, as the decontamination liquid flows, the inner surface of the pipe is uniformly decontaminated, and as a result, there is no opening for corrosion of the pipe metal, and material deterioration can be prevented.

つぎに、本発明の再循環ラインに気泡を送り込みながら
除染液を供給し−C除染づる方法の具体的実施例につい
て以下に述べる。対象はB W Rプラントの原子炉系
、具体的には原子炉再循環ラインε3内の敢)J能除染
Cある。この除染のための化学除染液はに1線で小した
部分a内にン°1人される。そしてこの化学除染液が原
子炉再循環ライン人口8a J)よびjl冒1811.
l、り原子炉圧力容器内1に流出するのを防止づるため
原子炉圧力容器1内には一定の圧力に気体が圧入させる
。このため化学除染期間中には除染液中に気泡として吹
き込んだ気体のΦだけ原子炉圧力容器内の気体圧力調節
弁13から抜き出し、原子炉圧力容器1内の気体圧力を
一定に保つ様にηる。この様な方法で実施した除染結果
を次表に示す。これは従来方法すなわち除染液中に気泡
を吹き込まない方法の結果と比較して示したものである
Next, a specific embodiment of the method of the present invention for -C decontamination by supplying a decontamination liquid while feeding air bubbles into a recirculation line will be described below. The target is the reactor system of the BWR plant, specifically the decontamination of the reactor recirculation line ε3. A chemical decontamination solution for this decontamination is poured into a small area a by one line. This chemical decontamination liquid then flows into the reactor recirculation lines 8a J) and 1811.
1. In order to prevent gas from flowing into the reactor pressure vessel 1, gas is forced into the reactor pressure vessel 1 at a constant pressure. For this reason, during the chemical decontamination period, Φ of the gas blown into the decontamination liquid as bubbles is extracted from the gas pressure control valve 13 in the reactor pressure vessel to keep the gas pressure in the reactor pressure vessel 1 constant. to η. The results of decontamination conducted using this method are shown in the table below. This is shown in comparison with the results of the conventional method, that is, a method that does not blow air bubbles into the decontamination solution.

放射能の除去効果を調べるljめにΔ、B、C1D、E
の5B所の地点において配管表面の放射線線量を測定し
た。
Δ, B, C1D, E to examine the radioactivity removal effect lj
The radiation dose on the pipe surface was measured at point 5B.

本発明においては測定した5地点において除染後は放射
線線量は3〜l0IIIR/hrまで低下した。
In the present invention, the radiation dose decreased to 3 to 10IIIR/hr after decontamination at the five measured points.

従来方法においては表に示す様に5〜351R/hrで
あることと比較すると本発明においては除染の効果が増
大し、また各場所向じ程度まで放射線線ωが低下しCい
ることがルγめられる。
Compared to the conventional method, which is 5 to 351 R/hr as shown in the table, the decontamination effect of the present invention is increased, and the radiation ω is reduced to the extent of C in each location. γ is praised.

[発明の効果] 本発明によれば除染液中に気泡を吹き込むことにより除
染時間を短縮でき、また均一に被対象物とする配管の内
面の除染することができるので被対象物の地金を除染液
により侵すことがなく材料に対しても悪影響を及ぼすこ
とがない効果がある。
[Effects of the Invention] According to the present invention, the decontamination time can be shortened by blowing air bubbles into the decontamination liquid, and the inner surface of the target piping can be uniformly decontaminated. It has the effect that the decontamination liquid does not attack the base metal and does not have any adverse effects on the materials.

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

図は本発明に係る原子炉系配管の除染方法を説明づるた
めのB W R/ラン1−の1原子炉系を小り系統図ひ
ある。 1・・・・・・・・・・・・原子炉圧力容器2・・・・
・・・・・・・炉 心 3・・・・・・・・・・・・ジェットポンプ4・・・・
・・・・・・・・気液分離器5・・・・・・・・・・・
・蒸気乾燥器6・・・・・・・・・・・・主蒸気ライン
7・・・・・・・・・・・・給水ライン8・・・・・・
・・・・・・原子炉再循環ライン9・・・・・・・・・
・・・再循環ポンプ10・・・・・・・・・・・・バル
ブ 11・・・・・・・・・・・・原子炉圧力調節用気体供
給ライン 12・・・・・・・・・・・・原子炉圧力調節用気体供
給ポンプ 13・・・・・・・・・・・・気体圧力調節弁14・・
・・・・・・・・・・バイパスライン15・・・・・・
・・・・・・切換バルブ16・・・・・・・・・・・・
除染液注入塵17・・・・・・・・ガス吹き込み口 a・・・・・・・・・・・・・・・除染液充填範囲△、
B、C,D、E −M 射線線m +11 定位16
The figure is a small system diagram of one nuclear reactor system of BWR/Run 1- for explaining the method of decontaminating reactor system piping according to the present invention. 1......Reactor pressure vessel 2...
......Furnace core 3...Jet pump 4...
...... Gas-liquid separator 5 ......
・Steam dryer 6... Main steam line 7... Water supply line 8...
・・・・・・Reactor recirculation line 9・・・・・・・・・
... Recirculation pump 10 ...... Valve 11 ...... Gas supply line for reactor pressure adjustment 12 ...... ... Gas supply pump 13 for reactor pressure adjustment ... Gas pressure control valve 14 ...
・・・・・・・・・Bypass line 15・・・・・・
・・・・・・Switching valve 16・・・・・・・・・・・・
Decontamination liquid injection dust 17... Gas inlet a ...... Decontamination liquid filling range △,
B, C, D, E -M Ray m +11 Localization 16

Claims (2)

【特許請求の範囲】[Claims] (1)沸騰水型原子力発電所の原子炉系配管の内面を化
学的に除染する方法において、前記原子炉系配管内に化
学除染液を流入するとともに、その化学除染液内に気泡
を吹き込むことを特徴とする原子炉系配管の除染方法。
(1) In a method of chemically decontaminating the inner surface of the reactor system piping of a boiling water nuclear power plant, a chemical decontamination liquid flows into the reactor system piping, and air bubbles are formed in the chemical decontamination liquid. A method of decontaminating nuclear reactor system piping characterized by injecting.
(2)吹き込む気体は空気、窒素、酸素、水素、アルゴ
ンから選らばれた少なくとも一種の気体であることを特
徴とする特許請求の範囲第1項記載の原子炉系配管の除
染方法。
(2) The method for decontaminating nuclear reactor system piping according to claim 1, wherein the gas to be blown is at least one type of gas selected from air, nitrogen, oxygen, hydrogen, and argon.
JP59110910A 1984-06-01 1984-06-01 Method of decontaminating nuclear reactor system piping Pending JPS60256100A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59110910A JPS60256100A (en) 1984-06-01 1984-06-01 Method of decontaminating nuclear reactor system piping

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59110910A JPS60256100A (en) 1984-06-01 1984-06-01 Method of decontaminating nuclear reactor system piping

Publications (1)

Publication Number Publication Date
JPS60256100A true JPS60256100A (en) 1985-12-17

Family

ID=14547740

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59110910A Pending JPS60256100A (en) 1984-06-01 1984-06-01 Method of decontaminating nuclear reactor system piping

Country Status (1)

Country Link
JP (1) JPS60256100A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02119984A (en) * 1988-10-29 1990-05-08 Nippon Shisetsu Hozen Kk Method for cleaning off fat and oil deposited in pipeline
JP2011027694A (en) * 2009-07-29 2011-02-10 Toshiba Corp Decontamination device of facility in nuclear power plant

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH02119984A (en) * 1988-10-29 1990-05-08 Nippon Shisetsu Hozen Kk Method for cleaning off fat and oil deposited in pipeline
JP2011027694A (en) * 2009-07-29 2011-02-10 Toshiba Corp Decontamination device of facility in nuclear power plant

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