JPH07104437B2 - Decontamination method for radioactive granular waste - Google Patents

Decontamination method for radioactive granular waste

Info

Publication number
JPH07104437B2
JPH07104437B2 JP62064877A JP6487787A JPH07104437B2 JP H07104437 B2 JPH07104437 B2 JP H07104437B2 JP 62064877 A JP62064877 A JP 62064877A JP 6487787 A JP6487787 A JP 6487787A JP H07104437 B2 JPH07104437 B2 JP H07104437B2
Authority
JP
Japan
Prior art keywords
radioactive
blast material
waste
granular waste
decontamination
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 - Fee Related
Application number
JP62064877A
Other languages
Japanese (ja)
Other versions
JPS63231299A (en
Inventor
孝雄 会津
克一 岩田
孫次 岡本
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.)
NGK Insulators Ltd
Chubu Electric Power Co Inc
Original Assignee
NGK Insulators Ltd
Chubu Electric Power Co Inc
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 NGK Insulators Ltd, Chubu Electric Power Co Inc filed Critical NGK Insulators Ltd
Priority to JP62064877A priority Critical patent/JPH07104437B2/en
Publication of JPS63231299A publication Critical patent/JPS63231299A/en
Publication of JPH07104437B2 publication Critical patent/JPH07104437B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Landscapes

  • Processing Of Solid Wastes (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)

Description

【発明の詳細な説明】 (産業上の利用分野) 本発明は、原子力発電所の配管内部等の研掃処理の際に
多量に発生する放射性粒状廃棄物の除染方法に関するも
のである。
Description: TECHNICAL FIELD The present invention relates to a method for decontaminating radioactive granular waste that is generated in large quantities during the blasting treatment of the inside of piping of a nuclear power plant.

(従来の技術) 例えば原子力発電所の配管内部等の錆落としのために
は、粒径が1mm程度のスチールショット等のブラスト材
を高圧水とともに配管内部等に噴射する方法が採用され
ている。この結果、放射性物質により汚染された多量の
ブラスト材と、錆や塗料の剥離被膜等との混合物が発生
することとなるが、従来はそのまま全量を放射性廃棄物
としてドラム缶に詰めて保管していたので、放射性廃棄
物の発生量の増加の原因のひとつとなっていた。しかる
に最近では増加する一方の放射性廃棄物の保管場所が重
大な社会問題となりつつあり、放射性廃棄物の発生量を
抑制することが望まれているため、上記のような放射性
粒状廃棄物についてもその処理方法の見直しが求められ
ていた。
(Prior Art) For example, in order to remove rust inside the piping of a nuclear power plant, a method of injecting blast material such as steel shot having a particle size of about 1 mm into the inside of the piping together with high-pressure water is adopted. As a result, a large amount of blast material contaminated with radioactive substances and a mixture of rust and paint peeling film are generated. Conventionally, the entire amount was stored as radioactive waste in drums. Therefore, it was one of the causes of the increase in the amount of radioactive waste. Recently, however, the ever increasing number of radioactive waste storage areas is becoming a serious social problem, and it is desired to reduce the amount of radioactive waste generated. A review of the processing method was required.

(発明が解決しようとする問題点) 本発明は上記したような従来の問題点を解決して、配管
内部等の研掃処理の際に多量に発生する放射性粒状廃棄
物を放射性廃棄物として取扱うべき部分と再使用できる
部分とに分別することにより放射性廃棄物の発生量を低
減させるとともに全体の合理的処分を可能にした放射性
粒状廃棄物の除染方法を目的として完成されたものであ
る。
(Problems to be Solved by the Invention) The present invention solves the above-mentioned conventional problems and handles a large amount of radioactive granular waste generated during the blasting treatment of the inside of a pipe or the like as radioactive waste. It was completed for the purpose of decontaminating a radioactive granular waste by reducing the amount of radioactive waste generated by separating it into an appropriate part and a reusable part, and also enabling the rational disposal of the whole.

(問題点を解決するための手段) 本発明は、スチール製のブラスト材を含む放射性粒状廃
棄物を分級処理して夾雑物と微粉化したブラスト材を除
去し、次に磁力分離により酸化鉄等を除去したうえ、除
染籠とその内部に設けられた中空円筒との間に薄層状に
充填して酸化鉄を溶解できる溶液中で超音波除染し、得
られたブラスト材を回収するとともに途中で分離された
物質を放射性廃棄物として処分することを特徴とするも
のであり、以下に実施例とともに更に詳細に説明する。
(Means for Solving Problems) According to the present invention, radioactive granular waste containing steel blast material is classified to remove contaminants and pulverized blast material, and then iron oxide or the like is magnetically separated. In addition to removing the blast material, ultrasonic decontamination is performed in a solution that can dissolve iron oxide by filling in a thin layer between the decontamination basket and the hollow cylinder provided inside, and the blast material obtained is collected It is characterized in that the substances separated on the way are disposed of as radioactive waste, which will be described in more detail below along with examples.

本発明において、スチール製のブラスト材を多量に含む
放射性粒状廃棄物は先ず第1図に示される振動篩機
(1)等により分級処理される。本実施例では上段の篩
(2)は例えば1500〜1700μの目開きを持ち、下段の篩
(3)は200〜300μの目開きを持つものである。上段の
篩(2)によって剥離した塗料被膜等の夾雑物が除去さ
れてシュート(4)へ排出され、また下段の篩(3)に
よって微粉化したブラスト材等が分離されやはりシュー
ト(4)へ排出される。この結果、300〜1500μの粒径
の残留物だけがシュート(5)からコンベア(6)上へ
の取出されるが、その約8割はブラスト材であり残部の
ほとんどは酸化鉄である。コンベア(6)の上方にはマ
グネット(7)が複数個設置されており、残留物をマグ
ネットに吸着されるスチール製のブラスト材とマグネッ
トに吸着されない酸化鉄及びその他の夾雑物とに磁力分
離する。そしてマグネットに吸着されない酸化物等は前
工程で分離されシュート(4)から排出された夾雑物と
ともに従来どおり放射性廃棄物としてドラム缶に詰めて
保管される。一方、マグネット(7)に吸着されたブラ
スト材は除染籠(8)の内部に充填され、第2図に示さ
れる超音波洗浄槽(9)において超音波除染される。こ
の超音波除染の効果を確実なものとするため、除染籠
(8)の中央部には中空円筒(10)が設けられており、
ブラスト材を除染籠と中空円筒との間に薄層状に充填で
きるようになっている。除染籠(8)は酸化鉄を溶解で
きるカセイソーダ溶液または硫酸溶液の入った超音波洗
浄槽(9)の内部に浸漬され、超音波発振子(11)から
発振される超音波によってブラスト材の表面の錆(酸化
鉄)その他の付着物が除去される。このようにして超音
波洗浄されたブラスト材は更にリンス槽(12)内で脱塩
水によって洗浄されたうえ放射能レベルのモニタリング
が行われ、放射能レベルが所定のレベル以下になったこ
とが確認されたブラスト材は回収されて再使用される。
In the present invention, the radioactive granular waste containing a large amount of steel blast material is first classified by the vibrating screener (1) shown in FIG. In the present embodiment, the upper sieve (2) has a mesh size of 1500 to 1700 μ, for example, and the lower sieve (3) has a mesh size of 200 to 300 μ. Contaminants such as paint films that have been peeled off by the upper screen (2) are removed and discharged to the chute (4), and finely blasted materials and the like are separated by the lower screen (3) and also to the chute (4). Is discharged. As a result, only the residue having a particle size of 300 to 1500 μ is taken out from the chute (5) onto the conveyor (6), about 80% of which is blast material and most of the rest is iron oxide. A plurality of magnets (7) are installed above the conveyor (6) to magnetically separate the residue into a steel blast material adsorbed by the magnet and iron oxide and other impurities not adsorbed by the magnet. . Oxides and the like that are not adsorbed on the magnet are stored in a drum as radioactive waste together with the contaminants separated in the previous step and discharged from the chute (4) as in the conventional case. On the other hand, the blast material adsorbed by the magnet (7) is filled inside the decontamination basket (8) and ultrasonically decontaminated in the ultrasonic cleaning tank (9) shown in FIG. In order to ensure the effect of this ultrasonic decontamination, a hollow cylinder (10) is provided in the center of the decontamination basket (8),
The blast material can be filled in a thin layer between the decontamination basket and the hollow cylinder. The decontamination basket (8) is immersed in an ultrasonic cleaning tank (9) containing a caustic soda solution or a sulfuric acid solution capable of dissolving iron oxide, and the blasting material of the blasting material is ultrasonically oscillated by the ultrasonic oscillator (11). Surface rust (iron oxide) and other deposits are removed. The blast material ultrasonically cleaned in this way was further cleaned with demineralized water in the rinse tank (12) and the radioactivity level was monitored, and it was confirmed that the radioactivity level fell below the prescribed level. The blast material is recovered and reused.

以上に説明した本発明の工程によれば、研掃に使用され
たグリッド材の約85%を回収することがきるので、使用
されたグリッド材の全量を廃棄していた従来法に比較し
て放射性廃棄物の発生量を1/2〜1/3に減少させることが
できる。また回収されたグリッド材の約6割は再使用で
きるので、スチール製、スレンレススチール製のいずれ
のグリッド材の場合にもその総使用量を半減させること
ができ、放射性粒状廃棄物の合理的処分が可能である。
According to the process of the present invention described above, it is possible to recover about 85% of the grid material used for blasting, so compared with the conventional method in which all the grid material used is discarded. The amount of radioactive waste generated can be reduced to 1/2 to 1/3. In addition, since about 60% of the collected grid material can be reused, it is possible to halve the total usage of both steel and stainless steel grid materials, and rational disposal of radioactive granular waste. Is possible.

(発明の効果) 本発明は以上の説明からも明らかなように、ブラスト材
を多量に含む放射性粒状廃棄物を放射性廃棄物として取
扱うべき部分とブラスト材として再使用できる部分とに
区分することにより放射性廃棄物の発生量を著しく低減
させることができるうえ、ブラスト材の総使用量をも減
少させることができる。よって本発明は特に原子力発電
所の配管内部等の研掃処理の際に多量に発生するスチー
ル製のブラスト材を多量に含む放射性粒状廃棄物の除染
方法として、産業の発展に寄与するところは極めて大き
いものである。
(Effects of the Invention) As is apparent from the above description, the present invention is achieved by dividing radioactive granular waste containing a large amount of blast material into a portion to be treated as radioactive waste and a portion that can be reused as blast material. Not only can the amount of radioactive waste generated be significantly reduced, but the total amount of blast material used can also be reduced. Therefore, the present invention particularly contributes to the development of the industry as a method for decontaminating radioactive granular waste containing a large amount of steel blast material, which is generated in large quantities during the blasting treatment of the inside of piping of a nuclear power plant. It is extremely large.

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

第1図は本発明の除染工程の前半部分を示す工程図、第
2図は同じく後半部分を示す工程図である。 (1):振動篩機、(7):マグネット、(8):除染
籠、(9):超音波洗浄槽、(10):中空円筒、(1
2):リンス槽。
FIG. 1 is a process diagram showing the first half of the decontamination process of the present invention, and FIG. 2 is a process diagram showing the latter half of the same. (1): Vibrating screener, (7): Magnet, (8): Decontamination basket, (9): Ultrasonic cleaning tank, (10): Hollow cylinder, (1
2): Rinse tank.

───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭60−178399(JP,A) 特開 昭56−46497(JP,A) ─────────────────────────────────────────────────── --Continued from the front page (56) References JP-A-60-178399 (JP, A) JP-A-56-46497 (JP, A)

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】スチール製のブラスト材を含む放射性粒状
廃棄物を分級処理して夾雑物と微粉化したブラスト材を
除去し、次に磁力分離により酸化鉄等を除去したうえ、
除染籠とその内部に設けられた中空円筒との間に薄層状
に充填して酸化鉄を溶解できる溶液中で超音波除染し、
得られたブラスト材を回収するとともに途中で分離され
た物質を放射性廃棄物として処分することを特徴とする
放射性粒状廃棄物の除染方法。
1. A radioactive granular waste containing a steel blast material is classified to remove impurities and finely divided blast material, and then iron oxide and the like are removed by magnetic separation.
Ultrasonic decontamination in a solution capable of dissolving iron oxide by filling it in a thin layer between the decontamination basket and the hollow cylinder provided inside it.
A method for decontaminating radioactive granular waste, which comprises recovering the obtained blast material and disposing of substances separated on the way as radioactive waste.
JP62064877A 1987-03-19 1987-03-19 Decontamination method for radioactive granular waste Expired - Fee Related JPH07104437B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62064877A JPH07104437B2 (en) 1987-03-19 1987-03-19 Decontamination method for radioactive granular waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62064877A JPH07104437B2 (en) 1987-03-19 1987-03-19 Decontamination method for radioactive granular waste

Publications (2)

Publication Number Publication Date
JPS63231299A JPS63231299A (en) 1988-09-27
JPH07104437B2 true JPH07104437B2 (en) 1995-11-13

Family

ID=13270791

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62064877A Expired - Fee Related JPH07104437B2 (en) 1987-03-19 1987-03-19 Decontamination method for radioactive granular waste

Country Status (1)

Country Link
JP (1) JPH07104437B2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0727073B2 (en) * 1990-03-20 1995-03-29 森川産業株式会社 Decontamination method and decontamination apparatus for objects contaminated with radioactivity, and decontamination method and decontamination apparatus for materials used for the decontamination
JP5313387B1 (en) * 2012-05-18 2013-10-09 公立大学法人県立広島大学 Methods for treating radioactive material contaminants

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6057039B2 (en) * 1979-09-26 1985-12-12 三菱マテリアル株式会社 Method for recovering coated nuclear fuel particles from overcoated nuclear fuel particles
EP0158743B1 (en) * 1984-01-26 1988-07-27 Ernst Schmutz GmbH Process and device for cleaning parts of plants which are contaminated by radioactivity

Also Published As

Publication number Publication date
JPS63231299A (en) 1988-09-27

Similar Documents

Publication Publication Date Title
CA1252415A (en) Decontaminating metal surfaces with chelating solution and electrolysis
US3895465A (en) Cleaning contaminated surfaces of nuclear power plants and recovery of removed surface particles
US4724853A (en) Method and apparatus for decontaminating solid surface
US5302324A (en) Method for decontaminating substances contaminated with radioactivity, and method for decontaminating the materials used for said decontamination
JPS60636B2 (en) Treatment method for radioactive waste liquid
JPH07104437B2 (en) Decontamination method for radioactive granular waste
US5236134A (en) Method of reclaiming glass from articles formed of leaded glass
US5503591A (en) Apparatus for decontaminating substances contaminated with radioactivity
CN115478183B (en) Method for removing uranium in waste liquid of radioactive detergent containing aminocarboxylic acid
KR101558739B1 (en) Method for decontamination of radioactive concrete waste
JP3666791B2 (en) Toner separation processing method and processing system for used toner cartridge
US5570468A (en) Method and apparatus for decontaminating substances contaminated with radioactivity
JPH1143324A (en) Formation of resource from shell
GB2266002A (en) A method of removing radioactive material from metallic objects
JP2909173B2 (en) Decontamination method of radioactive waste
GB2319259A (en) reducing radionucleide contamination of a metallic component
JP3149529B2 (en) Method and apparatus for decontaminating radioactive contaminants
JP2000249790A (en) Magnetic oscillating decontamination method of radioactive contaminant and device thereof
JPS5886498A (en) Decontaminating device
JP2002311193A (en) Decontamination device for radioactive contaminator
JP3504595B2 (en) Pretreatment method and pretreatment device for spent nuclear fuel
JPS6067897A (en) Method of recovering and treating piping washing material
JPH11197643A (en) Method for washing contaminated soil
JP2002202399A (en) Method for recycling lead contaminated with radioactive substance
JPH032596A (en) Decontamination device for metal contaminated with radioactivity

Legal Events

Date Code Title Description
LAPS Cancellation because of no payment of annual fees