JPH0395500A - Decontamination of equipment/member for fast breeder reactor - Google Patents

Decontamination of equipment/member for fast breeder reactor

Info

Publication number
JPH0395500A
JPH0395500A JP23152289A JP23152289A JPH0395500A JP H0395500 A JPH0395500 A JP H0395500A JP 23152289 A JP23152289 A JP 23152289A JP 23152289 A JP23152289 A JP 23152289A JP H0395500 A JPH0395500 A JP H0395500A
Authority
JP
Japan
Prior art keywords
decontamination
sodium
equipment
reducing
liquid
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
JP23152289A
Other languages
Japanese (ja)
Inventor
Masami Toda
正見 遠田
Tetsuo Morisue
森末 哲夫
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 JP23152289A priority Critical patent/JPH0395500A/en
Publication of JPH0395500A publication Critical patent/JPH0395500A/en
Pending legal-status Critical Current

Links

Abstract

PURPOSE:To intend decrement of worker's radioactive exposure by blowing high temperature argon gas and steam, to an equipment and the like on which a sodium and radioactivity stick, in order to remove the sodium and then by decontaminating them using an oxidizing alkaline decontaminating liquid and a reducing decontaminating liquid. CONSTITUTION:In a high temperature argon gas deterging process, the high temperature argon gas is blown to a valve and the like on which a sodium sticks and the sodium is coarsely removed. Then, in a steam deterging process, the steam is blown to, and the sticking sodium remaining on the equipment is converted into an hydroxide, and is removed. Subsequently, potassium permanganate is added to a sodium hyroxide solution recollected in a producing process of an oxidizing alkaline decontamination liquid, and an oxidizing alkaline decontaminating agent is produced. Decontamination work of the equipment from which the sodium is removed, is carried out by using the decontamination agent. Also, in a reducing decontamination process, a reducing decontamination work is carried out by using an oxalic acid. In this way, radioactivity sticking to the equipment and the like, can be removed by both the oxidizing alkaline decontamination process and the reducing decontamination process.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は液体ナトリウムを冷却材に使用する高速炉機器
の保守・点検の際に発生する放射能が付着した高速炉用
機器・部材の除染方法に関する。
[Detailed Description of the Invention] [Objective of the Invention] (Industrial Application Field) The present invention is directed to fast reactor equipment that is contaminated with radioactivity generated during maintenance and inspection of fast reactor equipment that uses liquid sodium as a coolant. Concerning decontamination methods for equipment and parts.

(従来の技術) 高速増殖炉(以下高速炉と記す)における機器の除染は
、従来汚染した機器を不活性ガスまたは空気洗浄したの
ち水蒸気洗浄し、次に水中浸漬等して付着ナトリウム及
び放射能を除去していた。
(Prior art) Equipment decontamination in fast breeder reactors (hereinafter referred to as fast reactors) is conventionally carried out by cleaning contaminated equipment with inert gas or air, cleaning it with steam, and then immersing it in water to remove adhering sodium and radiation. Noh was removed.

この除染方法は、機器の付着ナトリウムの除去に適して
いる。
This decontamination method is suitable for removing sodium adhering to equipment.

(発明が解決しようとする課題) しかしながら、この除染方法では母祠に付着した放射能
を完全に除去することができなかったため作業員の放射
線被曝が増加する問題があった。
(Problems to be Solved by the Invention) However, this decontamination method was unable to completely remove the radioactivity attached to the mother shrine, resulting in the problem of increased radiation exposure of workers.

また、蒸気洗浄一水中浸漬により発生する廃液は、その
ままの状態で保管していたため二次廃棄物が増加する課
題があった。
In addition, the waste liquid generated by steam cleaning and immersion in water was stored as is, resulting in an increase in secondary waste.

本発明は、この課題を解決するためになされたもので、
機器・部材に付着したナトリウムを高温不活性ガスと蒸
気洗浄で除去し、酸化性及び還元性除染を用いて放射能
を完全に除去して作業員の放射線被曝を低減し、さらに
二次廃棄物の発生量を低減する高速炉機器・部材の除染
方法を提供することにある。
The present invention was made to solve this problem,
Sodium adhering to equipment and components is removed by high-temperature inert gas and steam cleaning, and radioactivity is completely removed using oxidizing and reducing decontamination to reduce radiation exposure of workers, and secondary disposal is also carried out. The object of the present invention is to provide a method for decontaminating fast reactor equipment and components that reduces the amount of waste generated.

[発明の構成] (課題を解決するための手段) 本発明は、ナトリウム及び放射能が付着した機器・部材
類を、高温アルゴンガス除去工程で付着ナトリウムを粗
回収し、次に水蒸気洗浄工程で残留付着ナl・リウムを
洗浄し、次に第1段階除染として酸化性アルカリ除染工
程で過マンガン酸カリウムと水酸化ナトリウムの混合液
からなる酸化性アルカリ除染液で除染を行い、付着除染
液の水洗後、第2段階除染として還元性除染工程でシュ
ウ酸,クエン酸等のいずれかの還元性(有機酸)除染液
で除染を行い、その後に付着除染液を水洗することを特
徴とする。
[Structure of the Invention] (Means for Solving the Problems) The present invention roughly recovers the adhering sodium from equipment and components to which sodium and radioactivity have adhered in a high-temperature argon gas removal process, and then performs a steam cleaning process to remove the adhering sodium. The residual adhering sodium/lium is washed away, and then, as the first stage of decontamination, decontamination is carried out using an oxidizing alkaline decontamination solution consisting of a mixture of potassium permanganate and sodium hydroxide in the oxidizing alkaline decontamination process. After washing the adhesion decontamination solution with water, the second stage of decontamination is decontamination using a reducing (organic acid) decontamination solution such as oxalic acid or citric acid, followed by adhesion decontamination. It is characterized by washing the liquid with water.

また、酸化性アルカリ除染工程と還元性アルカリ除染工
程で発生する酸化性アルカリ除染廃液と還元性除染廃液
は廃液処理工程で安定化し、濃縮一乾燥一固化すること
を特徴とする。
In addition, the oxidizing alkali decontamination waste liquid and the reducing decontamination waste liquid generated in the oxidizing alkali decontamination process and the reducing alkali decontamination process are stabilized in the waste liquid treatment process, and are characterized by being concentrated, dried, and solidified.

(作 用) ナトリウム及び放射能が付着した機器・部材類に高温ア
ルゴンガスを吹き込むとナトリウムが蒸発しアルゴンガ
スと同伴して機器からナ1・リウムが粗除去される。
(Function) When high-temperature argon gas is blown into equipment and parts contaminated with sodium and radioactivity, the sodium evaporates and is accompanied by argon gas, roughly removing sodium and lithium from the equipment.

次に水蒸気を吹き込むと残留ナトリウムは水酸化物に変
換し、水洗除去される。機器・部材類に付着した放射能
は、アルゴンカス洗浄と水蒸気洗浄でナトリウムと同伴
して一部除去されるが、母材に付着した放射能は完全に
除去されない。そこで蒸気洗浄後の水蒸気を凝縮回収し
酸化剤を添加して酸化性アルカリ除染液を生威し、水蒸
気洗浄後にこの除染液を用いて除染を行う。次に還元性
除染液を用いて除染を行う。除染を行った後の除染廃液
は、混合安定化し濃縮一乾燥−固化して保管する。
Next, by blowing in steam, the residual sodium is converted into hydroxide and removed by washing with water. Radioactivity attached to equipment and parts is partially removed along with sodium through argon gas cleaning and steam cleaning, but radioactivity attached to base materials is not completely removed. Therefore, the water vapor after steam cleaning is condensed and recovered, an oxidizing agent is added to produce an oxidizing alkaline decontamination liquid, and this decontamination liquid is used for decontamination after steam cleaning. Next, decontamination is performed using a reducing decontamination solution. After decontamination, the decontamination waste liquid is mixed, stabilized, concentrated, dried, and solidified before being stored.

このように本発明ではナトリウム及び放射能が付着した
機器・部材類に高温アルゴンガスと水蒸気を吹き込み、
ナ1・リウムを除去し、次に酸化性アルカリ除染液と還
元性除染液を用いて除染を行うため、機器・部材類から
放射能を除去することができるため、作業員の放射線被
曝を低減することができる。また、除染廃液は混合安定
して濃縮乾燥一固化するため二次廃棄物を低減すること
ができる。
In this way, in the present invention, high-temperature argon gas and steam are blown into equipment and parts that are contaminated with sodium and radioactivity.
Since Na1 and Lium are removed and then decontamination is performed using an oxidizing alkaline decontamination solution and a reducing decontamination solution, radioactivity can be removed from equipment and parts, making it possible for workers to be exposed to radiation. Radiation exposure can be reduced. In addition, since the decontamination waste liquid is mixed stably, concentrated, dried, and solidified, secondary waste can be reduced.

(実施例) 以下、本発明に係る高速炉機器・部材類の除染方法の実
施例を第1.図によって説明する。高温アルゴンガス洗
浄工程でナトリウムが付着したバルプないしはポンプ等
の被除染機器・部材類に300〜500°Cのアルゴン
ガスを吹き込むとナトリウムは蒸発し、機器・部材類か
らナトリウムが粗除去される。蒸発したナトリウムはア
ルゴンガスに同伴しアルゴンガス浄化工程でアルゴンガ
スを冷却するとナトリウムがベーパトラップされ回収さ
れる。回収したナトリウムは高速炉の冷却材として再使
用することができる。付着ナトリウムを粗除去後、水蒸
気洗浄工程で、水蒸気を吹き付けると、機器・部材類に
残留する付着ナトリウムは水酸化物に変換し除去される
。水酸化ナトリウムが含有する水蒸気は水蒸気凝縮工程
で凝縮し水酸化ナトリウム溶液として回収される。
(Example) Hereinafter, an example of the method for decontaminating fast reactor equipment and parts according to the present invention will be described in Section 1. This will be explained using figures. When argon gas at 300 to 500°C is blown into decontaminated equipment and parts such as valves or pumps that have sodium adhering to them during the high-temperature argon gas cleaning process, the sodium evaporates and roughly removes sodium from the equipment and parts. . The evaporated sodium is accompanied by argon gas, and when the argon gas is cooled in the argon gas purification step, the sodium is vapor trapped and recovered. The recovered sodium can be reused as a coolant for fast reactors. After the adhering sodium is roughly removed, water vapor is sprayed in a steam cleaning step, and the adhering sodium remaining on the equipment and parts is converted into hydroxide and removed. The water vapor contained in sodium hydroxide is condensed in a steam condensation step and recovered as a sodium hydroxide solution.

高温アルゴンガ洗浄工程と水蒸気洗浄工程では5 機器・部材類に付着したナトリウムとナトリウム中に含
まれる放射能は除去できるが、機器・部材類の母材に付
着した放射能は完全に除去することは困難である。そこ
で化学除染剤を用いて母利に付着した放射能を除去する
The high-temperature argon gas cleaning process and steam cleaning process can remove sodium attached to equipment and parts and the radioactivity contained in sodium, but cannot completely remove the radioactivity attached to the base materials of equipment and parts. Have difficulty. Therefore, a chemical decontamination agent is used to remove the radioactivity attached to the motherboard.

第1段階の除染として、酸化性アルカリ除染液生或工程
で回収した水酸化ナトリウム溶液に酸化剤である過マン
ガン酸カリウム(K.Mn 04 )を添加し酸化性ア
ルカリ除染剤を生或ずる。この除染剤を用いてナトリウ
ムを除去した機器・部材類の除染を行う。除染後、水洗
工程で機器・部材類に付着している除染液を水洗する。
In the first stage of decontamination, potassium permanganate (K.Mn 04 ), an oxidizing agent, is added to the sodium hydroxide solution recovered in a certain process to produce an oxidizing alkaline decontamination solution. There is. This decontamination agent will be used to decontaminate equipment and parts from which sodium has been removed. After decontamination, the decontamination liquid adhering to equipment and parts is washed away with water during the washing process.

次に第2段階の除染として還元性除染工程でシュウ酸(
還元性除染液)を用い、還元性除染を行う。還元除染終
了後、水洗工程で機器・部材類に付着している除染剤を
水洗する。第2段階の除染後の水洗液は使用後、第1段
階の水洗水に使用する。
Next, as the second stage of decontamination, oxalic acid (
Perform reductive decontamination using a reducing decontamination solution (reducing decontamination solution). After reduction decontamination is completed, the decontamination agent adhering to equipment and parts is washed away with water in the washing process. After use, the rinsing liquid after decontamination in the second stage is used as the rinsing water in the first stage.

酸化性アルカリ除染工程と還元性除染工程で機器・部材
類に付着している放射能(60Co,54Mn等)を除
去でき、除染したバルブやポンプ6 等の機器・部材類を再使用することができる。
The oxidizing alkali decontamination process and the reducing decontamination process can remove radioactivity (60Co, 54Mn, etc.) attached to equipment and parts, making it possible to reuse decontaminated equipment and parts such as valves and pumps6. can do.

一方、第1段階の除染で使用した酸化性アルカリ除染液
(過マンガン酸カリウムと水酸化ナトリウムの混合液)
と第2段階で使用した還元性除染液(シュウ酸)及び水
洗水は、除染排液として発生するため排液処理工程で混
合する。過マンガン酸カリウムとシュウ酸を混合すると
以下の酸化還元反応が起こり安定化する。
On the other hand, the oxidizing alkaline decontamination solution (mixture of potassium permanganate and sodium hydroxide) used in the first stage of decontamination
The reducing decontamination liquid (oxalic acid) and washing water used in the second stage are generated as decontamination wastewater, so they are mixed in the wastewater treatment process. When potassium permanganate and oxalic acid are mixed, the following redox reaction occurs and becomes stable.

M n o −+ 5/2H 2 C 2 0 44 →M n 2” + 5 C O 2↑+5H”この安
定化した除染排液を加熱して、濃縮一乾燥固化して保管
する。
M n o −+ 5/2H 2 C 2 0 44 → M n 2” + 5 C O 2↑+5H” This stabilized decontamination waste liquid is heated, concentrated, dried and solidified, and then stored.

なお、還元性除染工程で使用した還元性除染液はシュウ
酸に限らずクエン酸,ギ酸等の有機酸を用いても同様の
効果が得られる。
Note that the reducing decontamination liquid used in the reducing decontamination step is not limited to oxalic acid, and similar effects can be obtained by using organic acids such as citric acid and formic acid.

次に上記実施例の効果を確認するために行った除染結果
を第2図によって説明する。第2図中、縦軸は表面汚染
量を任意単位量で示し、横軸は本発明の除染方法である
洗浄及び除染工程を示している。また、丸印は各工程で
除染した時の表面汚染量を示し、水平線aはバックグラ
ンドレベルを示している。この第2図から明らかなよう
に本発明に係る除染法を用いることにより機器・部材類
に付着したナトリウムはもちろん、放射能をパックグラ
ンドレベルまで下げることができ、除染した機器・部材
類を再使用することかできる。
Next, the results of decontamination carried out to confirm the effects of the above embodiment will be explained with reference to FIG. In FIG. 2, the vertical axis represents the amount of surface contamination in arbitrary units, and the horizontal axis represents the cleaning and decontamination steps of the decontamination method of the present invention. Further, the circles indicate the amount of surface contamination when decontaminated in each step, and the horizontal line a indicates the background level. As is clear from this Figure 2, by using the decontamination method according to the present invention, not only sodium adhering to equipment and parts, but also radioactivity can be reduced to the pack ground level, and the decontaminated equipment and parts can be reduced to the ground level. can be reused.

なお、本発明の実施態様を要約すれば次の通りである。The embodiments of the present invention can be summarized as follows.

■ 水蒸気洗浄後、水蒸気は水蒸気凝縮工程で水酸化ナ
トリウム溶液として回収し、酸化性アルカリ除染液生或
工程で回収した水酸化ナトリウム溶液と過マンガン酸カ
リウムとを混合して酸化性アルカリ除染工程の酸化性ア
ル力除染液として用いること。
■ After steam cleaning, the steam is recovered as a sodium hydroxide solution in the steam condensation process, and the sodium hydroxide solution recovered in the process is mixed with potassium permanganate to produce an oxidizing alkaline decontamination solution. Use as an oxidizing alkaline decontamination solution in the process.

■ 第2段階水洗後の使用済み水溶液は第1段階除染後
の水洗液として用いること。
■ The used aqueous solution after the 2nd stage water washing should be used as the rinsing solution after the 1st stage decontamination.

■ 第↓段階除染後と第2段階除染後に発生する酸化性
アルカリ除染排液と還元性除染排液は排液処理工程で混
合安定化し、濃縮一乾燥固化すること。
■ Oxidizing alkaline decontamination wastewater and reducing decontamination wastewater generated after the ↓ stage decontamination and the second stage decontamination should be mixed and stabilized in the wastewater treatment process, and then concentrated and dried to solidify.

[発明の効果] 本発明によれば、以下の効果を有している。[Effect of the invention] According to the present invention, the following effects are achieved.

(1)高温アルゴンガス洗浄及び水蒸気洗浄によりナト
リウムを除去し、酸化性アルカリ除染液及び還元性除染
液により放射能を除去できるため、作業員の放射線被曝
を低減することができる。
(1) Since sodium can be removed by high-temperature argon gas cleaning and steam cleaning, and radioactivity can be removed by oxidizing alkaline decontamination liquid and reducing decontamination liquid, radiation exposure of workers can be reduced.

(2)酸化性アルカリ除染液および還元性除染液は腐食
性がないため除染した機器・部材類の再使用が可能であ
る。
(2) Since oxidizing alkaline decontamination liquid and reducing decontamination liquid are not corrosive, decontaminated equipment and parts can be reused.

(3)除染廃液は混合安定化して凝縮一乾燥一固化でき
るため二次廃棄物を低減することができる。
(3) The decontamination waste liquid can be mixed, stabilized, condensed, dried, and solidified, so secondary waste can be reduced.

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

第1図は本発明に係る高速炉機器・部材の除染方法を示
すブロックフロー図、第2図は本発明の除染効果を示す
特性図である。 a・・・バックグランド 9 第 1 図
FIG. 1 is a block flow diagram showing a method for decontaminating fast reactor equipment and members according to the present invention, and FIG. 2 is a characteristic diagram showing the decontamination effect of the present invention. a...Background 9 Figure 1

Claims (1)

【特許請求の範囲】[Claims] ナトリウムおよび放射能が付着した機器・部材類を高温
アルゴンガス除去工程で付着ナトリウムを粗回収し、次
に水蒸気洗浄工程で残留付着ナトリウムを洗浄し、次に
第1段階除染として酸化性アルカリ除染工程で酸化性ア
ルカリ除染液を用いて除染を行い、付着除染液の水洗後
、第2段階除染として還元性除染工程で還元性除染液を
用いて除染を行い、その後に付着除染液を水洗すること
を特徴とする高速炉用機器・部材の除染方法。
Equipment and parts contaminated with sodium and radioactivity are subjected to a high-temperature argon gas removal process to roughly recover the adhering sodium, then a steam cleaning process to wash away the remaining adhering sodium, and then oxidizing alkali removal as the first stage of decontamination. Decontamination is performed using an oxidizing alkaline decontamination liquid in the contamination process, and after washing the adhering decontamination liquid with water, decontamination is performed using a reducing decontamination liquid in the reducing decontamination process as the second stage decontamination. A method for decontaminating fast reactor equipment and components, which comprises washing off the adhering decontamination liquid with water.
JP23152289A 1989-09-08 1989-09-08 Decontamination of equipment/member for fast breeder reactor Pending JPH0395500A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP23152289A JPH0395500A (en) 1989-09-08 1989-09-08 Decontamination of equipment/member for fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP23152289A JPH0395500A (en) 1989-09-08 1989-09-08 Decontamination of equipment/member for fast breeder reactor

Publications (1)

Publication Number Publication Date
JPH0395500A true JPH0395500A (en) 1991-04-19

Family

ID=16924807

Family Applications (1)

Application Number Title Priority Date Filing Date
JP23152289A Pending JPH0395500A (en) 1989-09-08 1989-09-08 Decontamination of equipment/member for fast breeder reactor

Country Status (1)

Country Link
JP (1) JPH0395500A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110447077A (en) * 2017-01-16 2019-11-12 俄罗斯联邦诺萨顿国家原子能公司 The method for handling radioactive solution

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110447077A (en) * 2017-01-16 2019-11-12 俄罗斯联邦诺萨顿国家原子能公司 The method for handling radioactive solution
JP2020505590A (en) * 2017-01-16 2020-02-20 ステート・アトミック・エナジー・コーポレーション・ロスアトム・オン・ビハーフ・オブ・ザ・ロシアン・フェデレーションState Atomic Energy Corporation ‘Rosatom’ On Behalf Of The Russian Federation How to handle radioactive solutions
CN110447077B (en) * 2017-01-16 2023-05-05 俄罗斯联邦诺萨顿国家原子能公司 Method for treating radioactive solution

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