JPH0381699A - Decontaminating method for radioactive refuse - Google Patents
Decontaminating method for radioactive refuseInfo
- Publication number
- JPH0381699A JPH0381699A JP21720389A JP21720389A JPH0381699A JP H0381699 A JPH0381699 A JP H0381699A JP 21720389 A JP21720389 A JP 21720389A JP 21720389 A JP21720389 A JP 21720389A JP H0381699 A JPH0381699 A JP H0381699A
- Authority
- JP
- Japan
- Prior art keywords
- dust
- decontaminated
- dry
- decontamination
- shape
- 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
- 238000000034 method Methods 0.000 title claims abstract description 21
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 9
- 239000000428 dust Substances 0.000 claims abstract description 28
- 238000005202 decontamination Methods 0.000 claims abstract description 27
- 230000003588 decontaminative effect Effects 0.000 claims abstract description 17
- 238000005422 blasting Methods 0.000 claims description 27
- 239000002699 waste material Substances 0.000 claims description 19
- 239000002901 radioactive waste Substances 0.000 claims description 12
- 239000003082 abrasive agent Substances 0.000 claims description 11
- 230000005855 radiation Effects 0.000 claims description 10
- 239000000356 contaminant Substances 0.000 claims description 4
- 239000000843 powder Substances 0.000 claims description 2
- 238000011084 recovery Methods 0.000 claims description 2
- 238000011109 contamination Methods 0.000 abstract description 8
- 229910000831 Steel Inorganic materials 0.000 description 4
- 239000007787 solid Substances 0.000 description 4
- 239000010959 steel Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000005259 measurement Methods 0.000 description 3
- MCMNRKCIXSYSNV-UHFFFAOYSA-N Zirconium dioxide Chemical compound O=[Zr]=O MCMNRKCIXSYSNV-UHFFFAOYSA-N 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 1
- 238000009390 chemical decontamination Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003973 paint Substances 0.000 description 1
- 238000005498 polishing Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 238000005488 sandblasting Methods 0.000 description 1
Landscapes
- Measurement Of Radiation (AREA)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は放射性廃棄物の除染を簡単かつ自動的に実施可
能な放射性廃棄物の除染方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a method for decontaminating radioactive waste that can be easily and automatically decontaminated.
（従来の技術）
従来、放射性廃棄物の除染方法として、電解研磨除染、
Ｒｅｄｏｘ除染、化学除染、ウェットブラスト除染等湿
式の方法が多用されている。しかしながら、これらの湿
式の除染方法では、多くの廃液が発生し、これらの廃液
は放射能を含んでいるため、そのまま廃棄することはで
きず、処理が面倒で処理のための設備も大型となる問題
があった。(Conventional technology) Conventionally, methods for decontaminating radioactive waste include electrolytic polishing decontamination,
Wet methods such as Redox decontamination, chemical decontamination, and wet blast decontamination are often used. However, these wet decontamination methods generate a lot of waste liquid, and because these waste liquids contain radioactivity, they cannot be disposed of as they are, and treatment is troublesome and requires large processing equipment. There was a problem.
そのため、乾式の方法として、一般産業で使用されてい
るドライブラスト方式を放射性廃棄物の除染方法に応用
することも考えられている。これは、板材、管材などの
放射性廃棄物における汚染は表面部分のみであり、表面
をドライブラストで物理的に研削することにより、十分
に除染することができることに着目したことによる。Therefore, as a dry method, it is also being considered to apply the dry blast method used in general industry to the decontamination method of radioactive waste. This is due to the fact that the contamination of radioactive waste such as plates and pipes is only on the surface, and that it is possible to sufficiently decontaminate the surface by physically grinding the surface with dry blasting.
（発明が解決しようとする課題）
しかしながら、ドライブラストの結果発生する二次廃棄
物は固形分を含むダストであり、このダストが放射能を
含んでいるため、そのまま従来のドライブラスト方式を
放射性廃棄物の除染に応用できない問題があった。(Problem to be solved by the invention) However, the secondary waste generated as a result of dry blasting is dust containing solid content, and this dust contains radioactivity. There was a problem that it could not be applied to the decontamination of objects.
また、ドライブラスト等による表面の研削をそのまま搬
送手段により被除染物を搬送してブラスト処理を行なう
自動化ラインに適用すると、除染すべき物体の形状によ
っては研削できない部分が生じ、完全に除染できない場
合があるとともに、自動化ラインの搬送位置によっては
被除染物の存在しない場所に無駄にブラスト処理を実施
することとなる場合があった。In addition, if surface grinding by dry blasting etc. is applied directly to an automated line in which the object to be decontaminated is transported and blasted using a conveying means, some parts may not be able to be ground depending on the shape of the object to be decontaminated, resulting in complete decontamination. In some cases, this is not possible, and depending on the transport position of the automated line, there are cases in which the blasting process is wasted in areas where the objects to be decontaminated do not exist.
本発明の目的は上述した課題を解消して、簡単な構成で
放射性廃棄物中から放射性物質の除去が可能な放射性廃
棄物の除染方法を提供しようとするものである。An object of the present invention is to solve the above-mentioned problems and to provide a method for decontaminating radioactive waste that can remove radioactive substances from radioactive waste with a simple configuration.
（課題を解決するための手段）
本発明の放射性廃棄物の除染方法は、密閉状態で、被除
染物体の放射線量を測定し、その形状を認識し、認識し
た形状に応じてドライブラスト処理を行ない、被除染物
体の表面に付着した放射性の汚染物質を粉体状にして除
去した後、ドライブラスト後の被除染物体の放射線量を
測定し、その放射線量が許容値以下のときは一般廃棄物
に準ずるものとして処理する除染工程と、
ブラスト処理後の研削材と主にダストである汚染物質と
を分別し、研削材を回収して再度使用する研削材回収工
程と、
ダストを含む排気ガスはフィルタによりダストを除去し
てから外部へ排出し、フィルタによりろ過されたダスト
はダストボックス内に貯留後処分する排ガス処理工程と
からなることを特徴とするものである。(Means for Solving the Problems) The radioactive waste decontamination method of the present invention measures the radiation dose of an object to be decontaminated in a sealed state, recognizes its shape, and performs dry blasting according to the recognized shape. After processing and removing the radioactive contaminants attached to the surface of the object to be decontaminated into powder, the radiation dose of the object to be decontaminated after dry blasting is measured, and the radiation dose is determined to be below the allowable value. a decontamination process in which the abrasives are treated as equivalent to general waste, and an abrasive recovery process in which the abrasives after blasting are separated from contaminants, mainly dust, and the abrasives are collected and used again. This method is characterized by an exhaust gas treatment process in which dust-containing exhaust gas is removed by a filter and then discharged to the outside, and the dust filtered by the filter is stored in a dust box and then disposed of.
（作 用）
上述した構成において、所定の除染工程のみを密閉状態
で実施するため、ドライブラスト時のダストの飛散をな
くすことができ、放射能による汚染を防止できるととも
に、装置の大型化を最小限に抑えることができる。(Function) In the above-mentioned configuration, only the prescribed decontamination process is carried out in a sealed state, so it is possible to eliminate dust scattering during dry blasting, prevent radioactive contamination, and reduce the size of the equipment. can be minimized.
また、被除染物の幅、長さ、高さ等の形状を認識し、ド
ライブラスト時に認識した幅、長さ、高さ等の形状に基
き、ドライブラストを実施する被除染物の部分を特定し
ているため、研削できない部分をなくし、完全な除染を
実施することができる。さらに、被除染物の存在しない
場所に、無駄にブラスト処理することもない。It also recognizes the shape of the object to be decontaminated, such as the width, length, and height, and identifies the part of the object to be dry blasted based on the shape, such as the width, length, and height recognized during dry blasting. Therefore, it is possible to eliminate parts that cannot be ground and perform complete decontamination. Furthermore, there is no need to wastefully perform blasting on areas where there are no objects to be decontaminated.
また、ドライブラスト後の放射能を含む研削材及びダス
トを分別して研削材は再利用しているため、除染の結果
発生する二次廃棄物を最小限におさえることが可能とな
る。Furthermore, since the abrasives and dust containing radioactivity after dry blasting are separated and the abrasives are reused, it is possible to minimize secondary waste generated as a result of decontamination.
除染後の廃棄物は、現在は規定がないが将来的に基準が
設けられたときは、一般の廃棄物に準ずるものとして処
理することができるため、放射性廃棄物の量を少なくす
ることができる。There are currently no regulations regarding waste after decontamination, but if standards are established in the future, it will be possible to treat the waste as equivalent to general waste, thereby reducing the amount of radioactive waste. can.
（実施例）
第１図は、本発明の放射性廃棄物の除染方法を実施する
装置の一構成を示す図である。第１図に示す装置におい
て、１は除染すべき所定形状の被除染物体、２は被除染
物体ｌを搬入位置２−１において載置して搬送し搬出位
置２−２で外部へ搬出する搬送路、３は被除染物体１の
放射線量を測定するとともにその形状を認識する形状認
識部、４は被除染物体１の除染を実施するドライブラス
ト部、５は除染後の被除染物体１の放射線量を測定して
除染の状態を判別する判別部である。このうち、形状認
識部３、ドライブラスト部４および判別部５を気密構造
とし、ドライブラスト部４におけるブラスト処理時の放
射能を含むダストの飛散を防止するよう構成して、除染
工程を実施している。(Example) FIG. 1 is a diagram showing the configuration of an apparatus for implementing the radioactive waste decontamination method of the present invention. In the apparatus shown in Fig. 1, 1 is an object to be decontaminated with a predetermined shape to be decontaminated, and 2 is an object to be decontaminated, which is placed at a carry-in position 2-1 and transported, and then transported to the outside at a carry-out position 2-2. 3 is a shape recognition unit that measures the radiation dose of the object to be decontaminated 1 and recognizes its shape; 4 is a dry blast unit that decontaminates the object to be decontaminated; 5 is after decontamination; This is a determination unit that determines the state of decontamination by measuring the radiation dose of the object 1 to be decontaminated. Among these, the shape recognition section 3, dry blast section 4, and discrimination section 5 have an airtight structure to prevent dust containing radioactivity from scattering during the blasting process in the dry blast section 4, and the decontamination process is carried out. are doing.
また、形状認識部３には、放射能測定装置３１と形状認
識装置３−２とを設け、被除染物体１の所期の放射能汚
染量を求めるとともに、被除染物体１の幅、長さ、高さ
等の形状を認識している。In addition, the shape recognition unit 3 is provided with a radioactivity measurement device 31 and a shape recognition device 3-2 to determine the expected amount of radioactive contamination of the object 1 to be decontaminated, and also to determine the width of the object 1 to be decontaminated. Recognizes shapes such as length and height.
ドライブラスト部４、には、ドライブラスト用のロボッ
ト４−１と回転テーブル４−２とを設け、形状認識装置
３−２により認識した形状に基づき、被除染物体１の表
面のみをむらなくブラスト処理できるよう構成している
。また、ドライブラスト部４の下部には研削材処理部４
−３を設け、ドライブラスト後の放射能を含むダストお
よびグリッドを、スクリューコンベア４−４およびパケ
ットコンベア４−５により、後述する分級器１１へ供給
できるよう構成している。判別部５には、放射能測定装
置５−１を設け、除染後の被除染物体１の放射能汚染量
を求めている。また、除染後の被除染物体１の放射能汚
染量が、一般廃棄物に準ずるものとして処理できるレベ
ル以下のときは、搬出位置２−２から外部へ搬出して一
般廃棄物に準ずるものとして処理するとともに、レベル
を満たさない場合は同一の除染操作を再度繰り返すよう
、後述の制御部７で制御している。The dry blast section 4 is equipped with a dry blast robot 4-1 and a rotary table 4-2, and based on the shape recognized by the shape recognition device 3-2, only the surface of the object to be decontaminated 1 is evenly coated. It is configured so that it can be blasted. In addition, an abrasive processing section 4 is provided at the bottom of the dry blast section 4.
-3 is provided, and the dust and grid containing radioactivity after dry blasting are configured to be supplied to a classifier 11, which will be described later, by a screw conveyor 4-4 and a packet conveyor 4-5. The determination unit 5 is provided with a radioactivity measuring device 5-1 to determine the amount of radioactive contamination of the object 1 to be decontaminated after decontamination. In addition, if the amount of radioactive contamination of the decontaminated object 1 after decontamination is below the level that can be treated as general waste, the object will be transported outside from the transport location 2-2 and treated as general waste. In addition, if the level is not satisfied, the same decontamination operation is repeated again by the control unit 7, which will be described later.
これらの形状認識部３、ドライブラスト部４および判別
部５には各別に管路６−１．６−２．６−３を設け、管
路６−１〜６−３を通して各部内の雰囲気を吸引して負
圧にできるよう構成して、汚染したダスト等の外部への
飛散を防止することができる。また、放射能測定装置３
−１．形状認識装置３−２、ロボット４−１、回転テー
ブル４−２、放射能測定装置５−１の動作は、すべて制
御部７により制御している。Each of the shape recognition section 3, dry blast section 4, and discrimination section 5 is provided with a pipe 6-1, 6-2, 6-3, and the atmosphere inside each part is controlled through the pipes 6-1 to 6-3. It is configured to be able to create negative pressure by suction, thereby preventing contaminated dust and the like from scattering to the outside. In addition, radioactivity measuring device 3
-1. The operations of the shape recognition device 3-2, robot 4-1, rotary table 4-2, and radioactivity measurement device 5-1 are all controlled by the control unit 7.
次に研削材回収工程として、上述した除染工程において
サンドブラスト部４からスクリューコンベア４−４およ
びパケットコンベア４−５を介して分級器１１に供給さ
れた放射能を含むダストおよびグリッド等の研削材を、
カスケード、サイクロン等の分級器１１において、グリ
ッドとその他の固形分及びダストに分別する。分別され
たグリッド以外の固形分を管路１２を通ってダストボッ
クス１３内に貯留するとともに、分別されたグリッドを
プラストマシン１４に供給して管路１５を介してロボッ
ト４−１から噴射してブラスト処理に再利用している。Next, as an abrasive collection step, abrasive materials such as radioactive dust and grids supplied from the sandblasting section 4 to the classifier 11 via the screw conveyor 4-4 and the packet conveyor 4-5 in the above-mentioned decontamination step. of,
In a classifier 11 such as a cascade or cyclone, the material is separated into grids, other solids, and dust. The solid content other than the separated grids passes through the pipe 12 and is stored in the dust box 13, and the separated grids are supplied to the blast machine 14 and are injected from the robot 4-1 through the pipe 15 to be blasted. Reused for processing.
また、排ガス処理工程として、分級時に発生する微粒の
ダストを管路１６を介して、上述した管路６−１〜６−
３より吸引される形状認識部３、ドライブラスト部４、
判別部５内の雰囲気とともにファン１７により吸引し、
逆洗可能なＩＩＥＰＡフィルタ１８により除塵できるよ
う構成している。ＨＥＰ＾フィルタ１８で除塵後のダス
トは分級器１１で分別された固形分と同様ダストボック
ス内に貯留して廃棄している。このように、逆洗可能な
フィルタを使用しているため、連続運転が可能となる。In addition, as an exhaust gas treatment process, fine dust generated during classification is passed through the pipe line 16 to the pipe lines 6-1 to 6-6-
3, a shape recognition section 3, a dry blast section 4,
The atmosphere inside the discriminator 5 is sucked by the fan 17,
It is constructed so that dust can be removed by a backwashable IIEPA filter 18. The dust after removal by the HEP filter 18 is stored in a dust box and disposed of in the same way as the solids separated by the classifier 11. Since a backwashable filter is used in this way, continuous operation is possible.
上述した構成の装置において、実際のドライブラスト処
理は以下のようになる。形状認識部３において、高さ、
幅、長さ等の形状を認識された被除染物体ｌここでは半
割パイプを、搬送路２によりドライブラスト部４に搬送
し、回転テーブル４−２上に移載する。ここで、認識さ
れた形状に基き、制御部７の制御のもと、ロボット１と
回転テーブル４−２とが協動してドライブラスト処理を
実施している。すなわち、第２図にその一例を示すよう
に、形状認識部３において認識された高さＨ１幅Ｗ、長
さＬおよび断面半径りに基き、被除染物体１の上下、左
右、前後の動く範囲を規制しながらロボット４−１およ
び回転テーブル４−２の動きを制御している。In the apparatus configured as described above, the actual dry blasting process is as follows. In the shape recognition unit 3, the height,
The object to be decontaminated l whose width, length, etc. have been recognized, here a halved pipe, is transported to the dry blast section 4 via the transport path 2 and transferred onto the rotary table 4-2. Here, based on the recognized shape, the robot 1 and the rotary table 4-2 cooperate to perform the dry blasting process under the control of the control unit 7. That is, as an example is shown in FIG. 2, based on the height H1 width W recognized by the shape recognition unit 3, the length L, and the cross-sectional radius, the object 1 to be decontaminated can move up and down, left and right, and back and forth. The movements of the robot 4-1 and rotary table 4-2 are controlled while regulating the range.
このように、乾燥状態で実施できるドライブラストでは
、発生する二次廃棄物はダストとなりフィルタで捕集で
きるため、放射能を含む二次廃棄物の処理を簡単に実施
することができる。また、物理的に表面を研削している
ため研削力が大きく、除染すべき廃棄物表面に多少の凹
凸、錆、塗膜等があっても問題なく研削することができ
る。また、ロボットを使用して認識した形状に基いてド
ライブラストを実施できるため、立体的な廃棄物も漏れ
なく除染でき、且つ廃棄物以外の部分（例えば、コンベ
アや壁面）に研削材が当たることを極力防止することが
でき、機器の信頼性を高め寿命を延ばすことが可能であ
る。In this way, in dry blasting that can be carried out in a dry state, the generated secondary waste becomes dust and can be collected by a filter, so that secondary waste containing radioactivity can be easily processed. In addition, since the surface is physically ground, the grinding force is large, and even if the surface of the waste to be decontaminated has some unevenness, rust, paint film, etc., it can be ground without any problems. In addition, since dry blasting can be performed based on the shape recognized using a robot, even three-dimensional waste can be decontaminated without leaking, and the abrasive material hits parts other than waste (e.g., conveyors and walls). This can be prevented as much as possible, increasing the reliability of equipment and extending its lifespan.
なお、ドライブラスト処理に用いる研削材として、直径
０．５〜５帥のスチールグリッドまたはアルミナ、ジル
コニア系の研削材を吐出圧４〜１０ｋｇ／Ｃ１１１でブ
ラスト処理すると好ましい。また、上述した構成の装置
において処理すべき廃棄物の形状は、平板、半割パイプ
、格子、Ｈ型鋼、■型鋼、大口径パイプ等が好ましく、
またパイプ状のものや大型のものは予じめ切断して研削
材が容易に当たるような形状とすると好ましい。As the abrasive used for the dry blasting process, it is preferable to blast a steel grid having a diameter of 0.5 to 5 mm or an alumina or zirconia based abrasive at a discharge pressure of 4 to 10 kg/C111. In addition, the shape of the waste to be treated in the apparatus having the above-mentioned configuration is preferably a flat plate, a halved pipe, a lattice, an H-shaped steel, a ■-shaped steel, a large diameter pipe, etc.
In addition, it is preferable to cut pipe-shaped or large-sized objects in advance so that they can be easily hit by the abrasive material.
実際に第工図に示す装置を使用して、第３図に示す長さ
Ｌ＝２６０皿、高さＨ＝６５餉、厚さｔ＝５ｍｔ１１で
表面積が約６５０ｃｒＡのＬ型アングル材を廃棄物とし
て、本発明の除染方法を実施した。ブラスト条件は、０
．５〜１．５恥のスチールグリッドを研削材とし、圧力
４．５ ｋｇ／ｃｗｔ、風量１．２ Ｎｍ’／ｈ 、時
間５分であった。その結果、ブラスト前の汚染量が２Ｘ
１０−’μＣｉ ／ ｃｎｌであった廃棄物をブラスト
後２ＸＩＯ−’μＣｉ／ｃｍ以下にまで除染することが
できた。Actually, using the equipment shown in the construction drawing, the L-shaped angle material shown in Fig. 3 with length L = 260 plates, height H = 65 plates, thickness t = 5 mt11, and surface area of about 650 crA is disposed of as waste. The decontamination method of the present invention was carried out as follows. Blast conditions are 0
．． A steel grid of 5 to 1.5 mm was used as the abrasive, the pressure was 4.5 kg/cwt, the air volume was 1.2 Nm'/h, and the time was 5 minutes. As a result, the amount of contamination before blasting is 2X
It was possible to decontaminate waste that was 10-'μCi/cnl to less than 2XIO-'μCi/cm after blasting.
本発明は上述した実施例にのみ限定されるものではなく
、幾多の変形、変更が可能である。例えば、上述した実
施例では、ドライブラスト部４におけるブラスト処理時
に、被除染物体１を回転テーブル４−２上で回転できる
よう構成したが、必要に応じて例えば反転機構等を付加
することにより、よりブラスト処理を効果的に実施する
ことができる。また、判別部５においては、放射線量の
測定のみを実施したが、例えば重量測定等必要に応じて
検査項目を増加できることはいうまでもない。The present invention is not limited only to the embodiments described above, and numerous modifications and changes are possible. For example, in the embodiment described above, the object 1 to be decontaminated is configured to be rotated on the rotary table 4-2 during the blasting process in the dry blast section 4, but if necessary, for example, a reversing mechanism or the like may be added. , blasting can be carried out more effectively. In addition, although only the radiation dose was measured in the determination section 5, it goes without saying that the number of inspection items can be increased as necessary, such as weight measurement, for example.
（発明の効果）
以上の説明から明らかなように、本発明の放射性廃棄物
の除染方法によれば、所定の除染工程のみを密閉状態で
実施しているため、ドライブラスト時のダストの飛散を
なくすことができるとともに、装置の大型化を最小限に
抑えることができる。(Effects of the Invention) As is clear from the above explanation, according to the method for decontaminating radioactive waste of the present invention, only the predetermined decontamination process is carried out in a sealed state, so that the dust during dry blasting is It is possible to eliminate scattering and to minimize the increase in size of the device.
また、被除染物の所定の形状を認識し、認識した形状に
基いてドライブラストを実施する被除染物の部分を特定
しているため、研削できない部分をなくし、完全な除染
を実施することができる。In addition, since the predetermined shape of the object to be decontaminated is recognized and the parts of the object to be dry blasted are specified based on the recognized shape, parts that cannot be ground are eliminated and complete decontamination can be carried out. I can do it.
第１図は本発明の放射性廃棄物の除染方法を実施する装
置の一構成を示す図、
第２図はドライブラスト時の状態を示す園、第３図は被
除染物の一例の形状を示す図である。
１・・・被除染物体 ２・・・搬送路３・・・形
状認識部 ４・・・ドライブラスト部５・・・判
別部 ７・・・制御部１１・・・分級器
１３・・・ダストボックス１４・・・ブラスト
マシン
１８・・・）ＩＥＰＡフィルタ
１７・・・ファンFigure 1 is a diagram showing the configuration of an apparatus for carrying out the radioactive waste decontamination method of the present invention, Figure 2 is a diagram showing the state during dry blasting, and Figure 3 is an example of the shape of an object to be decontaminated. FIG. 1... Object to be decontaminated 2... Conveyance path 3... Shape recognition section 4... Dry blast section 5... Discrimination section 7... Control section 11... Classifier
13...Dust box 14...Blast machine 18...) IEPA filter 17...Fan
Claims (1)
形状を認識し、認識した形状に応じてドライブラスト処
理を行ない、被除染物体の表面に付着した放射性の汚染
物質を粉体状にして除去した後、ドライブラスト後の被
除染物体の放射線量を測定し、その放射線量が許容値以
下のときは一般廃棄物に準ずるものとして処理する除染
工程と、 ブラスト処理後の研削材と主にダストである汚染物質と
を分別し、研削材を回収して再度使用する研削材回収工
程と、 ダストを含む排気ガスはフィルタによりダストを除去し
てから外部へ排出し、フィルタによりろ過されたダスト
はダストボックス内に貯留後処分する排ガス処理工程と
からなることを特徴とする放射性廃棄物の除染方法。[Claims] 1. In a sealed state, the radiation dose of the object to be decontaminated is measured, its shape is recognized, and dry blasting is performed according to the recognized shape to remove the radiation that adheres to the surface of the object to be decontaminated. Decontamination involves removing radioactive contaminants in powder form, measuring the radiation dose of the object to be decontaminated after dry blasting, and treating the object as equivalent to general waste if the radiation dose is below the permissible value. The abrasive material recovery process separates the abrasive material after blasting from contaminants, mainly dust, and collects the abrasive material for reuse. The dust-containing exhaust gas is removed by a filter. A method for decontaminating radioactive waste, characterized by comprising an exhaust gas treatment step in which dust is discharged to the outside and filtered by a filter, and the dust is stored in a dust box and then disposed of.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP21720389A JPH0381699A (en) | 1989-08-25 | 1989-08-25 | Decontaminating method for radioactive refuse |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP21720389A JPH0381699A (en) | 1989-08-25 | 1989-08-25 | Decontaminating method for radioactive refuse |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0381699A true JPH0381699A (en) | 1991-04-08 |
Family
ID=16700484
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP21720389A Pending JPH0381699A (en) | 1989-08-25 | 1989-08-25 | Decontaminating method for radioactive refuse |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0381699A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5209964A (en) * | 1990-11-20 | 1993-05-11 | Kitagawa Industries Co., Ltd. | Conductive sheet for shielding electromagnetic waves |
| JP2005337778A (en) * | 2004-05-25 | 2005-12-08 | Chubu Electric Power Co Inc | Method for decontamination treatment of waste material for heat-transfer pipe in water supply heater and cleaving cutter used for implementation of such method |
| JP2011102812A (en) * | 2011-01-20 | 2011-05-26 | Japan Atomic Energy Agency | Method and device for decontaminating regions near the surface contaminated by radioactive isotope without remelting, re-diffusion and re-contamination due to athermal laser peeling |
| JP2014059163A (en) * | 2012-09-14 | 2014-04-03 | Ube Machinery Corporation Ltd | Scrap processing system and scrap processing method |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59216100A (en) * | 1983-05-24 | 1984-12-06 | 株式会社東芝 | Decontamination device for equipment contaminated with radioactivity |
| JPS6484198A (en) * | 1987-09-28 | 1989-03-29 | Toshiba Corp | Decontamination system for radioactive waste |
-
1989
- 1989-08-25 JP JP21720389A patent/JPH0381699A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59216100A (en) * | 1983-05-24 | 1984-12-06 | 株式会社東芝 | Decontamination device for equipment contaminated with radioactivity |
| JPS6484198A (en) * | 1987-09-28 | 1989-03-29 | Toshiba Corp | Decontamination system for radioactive waste |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5209964A (en) * | 1990-11-20 | 1993-05-11 | Kitagawa Industries Co., Ltd. | Conductive sheet for shielding electromagnetic waves |
| JP2005337778A (en) * | 2004-05-25 | 2005-12-08 | Chubu Electric Power Co Inc | Method for decontamination treatment of waste material for heat-transfer pipe in water supply heater and cleaving cutter used for implementation of such method |
| JP2011102812A (en) * | 2011-01-20 | 2011-05-26 | Japan Atomic Energy Agency | Method and device for decontaminating regions near the surface contaminated by radioactive isotope without remelting, re-diffusion and re-contamination due to athermal laser peeling |
| JP2014059163A (en) * | 2012-09-14 | 2014-04-03 | Ube Machinery Corporation Ltd | Scrap processing system and scrap processing method |
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