JP2013195427A - Method of disposing of secondary radioactive waste - Google Patents
Method of disposing of secondary radioactive waste Download PDFInfo
- Publication number
- JP2013195427A JP2013195427A JP2013055233A JP2013055233A JP2013195427A JP 2013195427 A JP2013195427 A JP 2013195427A JP 2013055233 A JP2013055233 A JP 2013055233A JP 2013055233 A JP2013055233 A JP 2013055233A JP 2013195427 A JP2013195427 A JP 2013195427A
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- JP
- Japan
- Prior art keywords
- concrete
- mixed
- secondary waste
- water
- container
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- 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.)
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Classifications
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B28—WORKING CEMENT, CLAY, OR STONE
- B28C—PREPARING CLAY; PRODUCING MIXTURES CONTAINING CLAY OR CEMENTITIOUS MATERIAL, e.g. PLASTER
- B28C5/00—Apparatus or methods for producing mixtures of cement with other substances, e.g. slurries, mortars, porous or fibrous compositions
- B28C5/08—Apparatus or methods for producing mixtures of cement with other substances, e.g. slurries, mortars, porous or fibrous compositions using driven mechanical means affecting the mixing
- B28C5/10—Mixing in containers not actuated to effect the mixing
- B28C5/12—Mixing in containers not actuated to effect the mixing with stirrers sweeping through the materials, e.g. with incorporated feeding or discharging means or with oscillating stirrers
- B28C5/1238—Mixing in containers not actuated to effect the mixing with stirrers sweeping through the materials, e.g. with incorporated feeding or discharging means or with oscillating stirrers for materials flowing continuously through the mixing device and with incorporated feeding or discharging devices
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B09—DISPOSAL OF SOLID WASTE; RECLAMATION OF CONTAMINATED SOIL
- B09B—DISPOSAL OF SOLID WASTE
- B09B3/00—Destroying solid waste or transforming solid waste into something useful or harmless
- B09B3/20—Agglomeration, binding or encapsulation of solid waste
- B09B3/25—Agglomeration, binding or encapsulation of solid waste using mineral binders or matrix
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/16—Processing by fixation in stable solid media
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
Abstract
Description
本発明は、原子力設備の構成部材を、水と水に混入された研磨剤との混合物を高圧力下で供給して行なわれる切断法で解体した時に発生する放射性二次廃棄物の処理方法に関する。 The present invention relates to a method for treating radioactive secondary waste generated when dismantling components of nuclear power equipment by a cutting method performed by supplying water and a mixture of abrasives mixed in water under high pressure. .
原子力設備を廃炉にする場合には、原子炉圧力容器やこの容器内に取付けられた部品などの高度に汚染された、あるいは高活性度の構成部材は放射線防護の理由から水中で熱的な、あるいは機械的な分離方法により解体されなければならない。鋸切断やフライス切断のようないわゆる低温の機械的分離法の他に、水・研磨剤懸濁液切断法(WASS法)または水・研磨剤噴射切断法(WAIS法)とも呼ばれる分離方法が使用され、この切断法では水と水に混入された研磨剤とが加圧噴射され、構成部材の解体に使用される。切断時には切断面結合物質が一緒に出てくるので、汚染金属物質あるいは活性金属物質と研磨剤との混合物が発生する。WASSあるいはWAISと略記される上記の分離方法の利点は、解体中に構成部材の溶接部において開放される機械的な応力、特に鋸切断において鋸刃または鋸チェーンを固着させることがある応力に対し柔軟性が高く、影響を受けにくいことにある。 When decommissioning a nuclear installation, highly contaminated or highly active components such as reactor pressure vessels and parts mounted in these vessels are thermally protected in water for reasons of radiation protection. Or must be dismantled by mechanical separation methods. In addition to so-called low-temperature mechanical separation methods such as sawing and milling, a separation method called water / abrasive suspension cutting method (WASS method) or water / abrasive jet cutting method (WAIS method) is used. In this cutting method, water and an abrasive mixed in the water are pressure-injected and used to disassemble the constituent members. Since the cut surface bonding material comes out together at the time of cutting, a mixture of contaminating metal material or active metal material and abrasive is generated. The advantages of the above-mentioned separation methods, abbreviated as WASS or WAIS, are the advantages of mechanical stresses that are released at the welds of components during dismantling, especially those that can cause the saw blade or saw chain to stick in saw cutting. It is flexible and not easily affected.
しかし、この水噴射切断法の重大な欠点は、その際に発生する二次廃棄物である。この二次廃棄物は、研磨剤と切断時に切除される切断部物質とで形成され、その重量は、最も不都合な場合には、解体された構成部材の自重とほぼ同一オーダーである。この二次廃棄物は解体領域で水槽の底から流体サイクロンで吸い出され、そこで遠心分離機により水分離される。この分離された混合物は、通常は珪砂である研磨剤の他に、切断部断面からの汚染物質あるいは活性物質を含むので、この混合物は放射性廃棄物として処理されなければならず、その調整のために多額の費用と多数の最終保管容器が必要となる。 However, a serious disadvantage of this water jet cutting method is the secondary waste generated at that time. This secondary waste is formed by the abrasive and the cutting material that is cut off during cutting, and its weight is, in the most inconvenient case, of the same order as the weight of the disassembled component. This secondary waste is sucked out by a fluid cyclone from the bottom of the water tank in the dismantling region, where it is separated into water by a centrifuge. In addition to the abrasive, which is usually silica sand, this separated mixture contains contaminants or active substances from the cut section, so this mixture must be treated as radioactive waste and for its adjustment Requires a large amount of money and a large number of final storage containers.
そこで本発明の課題は、原子力設備の構成部材を、水と水に混入された研磨剤との混合物による切断法で解体した時に発生する放射性二次廃棄物を著しい低コストで処理できる方法を提供することにある。 Therefore, an object of the present invention is to provide a method capable of processing radioactive secondary waste generated at the time of dismantling a component of a nuclear facility by a cutting method using a mixture of water and an abrasive mixed in water at a significantly low cost. There is to do.
この課題は本発明により、請求項1に記載の特徴を備えた方法により解決される。本方法では研磨剤と解体された構成部材の切断部物質との混合物からなる放射性二次廃棄物が非汚染コンクリートに混入され、この混合コンクリートが放射性一次廃棄物の最終保管容器に注入される。 This problem is solved according to the invention by a method with the features of claim 1. In this method, radioactive secondary waste composed of a mixture of abrasives and dismantled component material is mixed into non-contaminated concrete, and this mixed concrete is injected into the final storage container for radioactive primary waste.
本発明は、解体時に発生する研磨剤と切断部物質の混合物を、放射性一次廃棄物を容れた最終保管容器、または中間保管容器に注入される非汚染コンクリート(Reinbeton)、すなわち、放射線で汚染されていないコンクリートに、現行の放射線防護基準を守ることが保証される程度に混入することができるという考えに基づいており、これによりWASS法あるいはWAIS法で発生する放射性二次廃棄物の処理のための経費と保管の必要性を低減することができる。 In the present invention, a mixture of abrasive and cutting material generated at the time of dismantling is contaminated with non-contaminated concrete (Reinbeton) that is injected into a final storage container containing radioactive primary waste or an intermediate storage container, that is, radiation. It is based on the idea that it can be mixed with concrete to the extent that it is guaranteed to comply with the current radiation protection standards, so that it can be used for the treatment of radioactive secondary waste generated by the WASS or WAIS method. Cost and storage requirements can be reduced.
切断時に発生する二次廃棄物を解体水槽の清掃時に吸い出し、遠心分離機で機械的に分離し、事前に乾燥することなく、研磨剤と切断部物質とからなる流動性混合物として非汚染コンクリートに混入すれば、二次廃棄物の処理経費の更なる低減が達成される。 Secondary waste generated at the time of cutting is sucked out at the time of cleaning the dismantling water tank, mechanically separated by a centrifuge, and converted into non-contaminated concrete as a fluid mixture of abrasive and cutting material without drying in advance. If mixed, further reduction in the cost of treating secondary waste can be achieved.
本方法の別の有利な実施形態によれば、この二次廃棄物は押出機の中で非汚染コンクリートと混合され、この押出機により保管容器に注入される。 According to another advantageous embodiment of the method, this secondary waste is mixed with uncontaminated concrete in an extruder and injected into a storage container by this extruder.
二次廃棄物の混入量は、この二次廃棄物と非汚染コンクリートとの混合コンクリートの硬化後の破壊強度が少なくとも10N/mm2となるような量だけ、二次非汚染コンクリートに混入するのが望ましい。 The amount of secondary waste mixed into the secondary non-contaminated concrete is such that the fracture strength after hardening of the mixed concrete of this secondary waste and non-contaminated concrete is at least 10 N / mm 2 . Is desirable.
本方法の別の有利な実施形態によれば、前記容器はその上部を非汚染コンクリートで充填するのが望ましく、これによって、容器外部の放射線量を低減できるだけでなく、容器の取外し可能な閉鎖蓋に対して汚染のない閉鎖を保証することができる。 According to another advantageous embodiment of the method, it is desirable that the container is filled with non-contaminated concrete at the top, thereby not only reducing the radiation dose outside the container, but also a removable closure lid for the container. Against pollution-free closure.
この容器は好ましくは鋼製容器であり、その内壁が予め非汚染コンクリートで固められている。
図により本発明を詳細に説明する。
This container is preferably a steel container, the inner wall of which has been previously solidified with non-contaminated concrete.
The present invention will be described in detail with reference to the drawings.
図1によれば、ほぼ長方形の箱状の容器2の中に、原子力設備の構成部材を解体した時にでた多数の切断された部材4が入っている。この容器2は鋼製外被6を有し、その内壁は5〜15cmの厚さの非汚染コンクリートで内張りされている。これら複数の切断された部材4の間の空洞部8に混合コンクリート10が充填される。この混合コンクリート10は非汚染コンクリートと、研磨剤および切断部物質を含んだ二次廃棄物Sとの混合物である。このために、押出機12に供給された流動性を有する非汚染コンクリートRに二次廃棄物Sが混入され、フレキシブルホース14を通って遠隔操作で容器2に導かれる。
According to FIG. 1, a large number of cut members 4 formed when disassembling components of a nuclear facility are contained in a substantially rectangular box-shaped container 2. The container 2 has a steel jacket 6 whose inner wall is lined with non-contaminated concrete having a thickness of 5 to 15 cm. The
処理する二次廃棄物Sの量を低減すべく、水・研磨剤懸濁液切断法で発生し、解体領域から吸い出された、未だ水を含んだ二次廃棄物Sは遠心分離機で機械的に水分離され、これにより、この二次廃棄物Sを研磨剤と切断部物質とからなる流動性を有する混合物として、事前に乾燥する必要なしに、押出機12に供給することができる。 In order to reduce the amount of secondary waste S to be processed, the secondary waste S still containing water generated by the water / abrasive suspension cutting method and sucked out from the dismantling area is removed with a centrifuge. The secondary waste S is mechanically water-separated, and can be supplied to the extruder 12 as a fluid mixture composed of an abrasive and a cutting part material without the need for drying in advance. .
最大許容充填高さよりも低い、予め決められた充填高さHに達すると、二次廃棄物Sの供給は停止される。容器2の上部領域Bは非汚染コンクリートRの層で密封されるので、一般に同様に事前にコンクリート固化された蓋が無くなるという最も考えにくいケースでも、汚染された混合コンクリート10が外部領域に露出することはない。
When a predetermined filling height H that is lower than the maximum allowable filling height is reached, the supply of secondary waste S is stopped. Since the upper region B of the container 2 is sealed with a layer of non-contaminated concrete R, the contaminated mixed
2 容器
4 解体済みの切断部材
6 鋼製外被
8 空洞部
10 混合コンクリート
12 押出機
14 ホース
S 二次廃棄物
R 非汚染コンクリート
H 容器の高さ
2 Container 4 Disassembled cutting member 6 Steel jacket 8
S Secondary waste
R Non-contaminated concrete
H Container height
Claims (6)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE102012204348A DE102012204348B3 (en) | 2012-03-20 | 2012-03-20 | Method for disposing radioactive secondary waste that occurs during cutting of component of nuclear installation, involves adding clean concrete as pourable or flowable mixture of abrasive and concrete without previous drying |
DE102012204348.9 | 2012-03-20 |
Publications (1)
Publication Number | Publication Date |
---|---|
JP2013195427A true JP2013195427A (en) | 2013-09-30 |
Family
ID=48465025
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2013055233A Pending JP2013195427A (en) | 2012-03-20 | 2013-03-18 | Method of disposing of secondary radioactive waste |
Country Status (3)
Country | Link |
---|---|
JP (1) | JP2013195427A (en) |
CH (1) | CH706308A2 (en) |
DE (1) | DE102012204348B3 (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN107812781B (en) * | 2017-12-07 | 2023-09-12 | 河南核净洁净技术有限公司 | Equipment and method for disassembling low-radioactivity close-pleated waste filter |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS61111499A (en) * | 1984-11-06 | 1986-05-29 | 太平洋セメント株式会社 | Method of disposing waste |
JPS61287601A (en) * | 1985-06-14 | 1986-12-18 | 電気化学工業株式会社 | Treating vessel for waste |
JPH02311799A (en) * | 1989-05-29 | 1990-12-27 | Science & Tech Agency | Method and device for dismantlement of concrete structure of nuclear reactor |
JP2001343488A (en) * | 2000-06-01 | 2001-12-14 | Mitsubishi Materials Corp | Processing method for radioactive concrete |
JP2002131481A (en) * | 2000-10-26 | 2002-05-09 | Toshiba Corp | Method of solidification of radioactive waste |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3901783A1 (en) * | 1989-01-21 | 1990-08-02 | Kernforschungsz Karlsruhe | Method for the final storage of weakly contaminated building rubble from the demolition of nuclear installations |
DE4023118A1 (en) * | 1990-07-20 | 1992-01-30 | Kernforschungsz Karlsruhe | Conditioning lightly contaminated nuclear plant rubble - to obtain particles for concrete prodn., comprises crushing to suitable particle size and sepg. non-crushable fractions |
JP2003502623A (en) * | 1999-06-14 | 2003-01-21 | パウル・シェラー・インスティトゥート | Radioactive waste disposal |
-
2012
- 2012-03-20 DE DE102012204348A patent/DE102012204348B3/en not_active Expired - Fee Related
-
2013
- 2013-03-13 CH CH00599/13A patent/CH706308A2/en not_active Application Discontinuation
- 2013-03-18 JP JP2013055233A patent/JP2013195427A/en active Pending
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS61111499A (en) * | 1984-11-06 | 1986-05-29 | 太平洋セメント株式会社 | Method of disposing waste |
JPS61287601A (en) * | 1985-06-14 | 1986-12-18 | 電気化学工業株式会社 | Treating vessel for waste |
JPH02311799A (en) * | 1989-05-29 | 1990-12-27 | Science & Tech Agency | Method and device for dismantlement of concrete structure of nuclear reactor |
JP2001343488A (en) * | 2000-06-01 | 2001-12-14 | Mitsubishi Materials Corp | Processing method for radioactive concrete |
JP2002131481A (en) * | 2000-10-26 | 2002-05-09 | Toshiba Corp | Method of solidification of radioactive waste |
Also Published As
Publication number | Publication date |
---|---|
CH706308A2 (en) | 2013-09-30 |
DE102012204348B3 (en) | 2013-06-13 |
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