JPS6037000A - Method for neutralizing iron scrap and/or steel scrap contaminated by radiation and use to storage vessel of iron and steel obtained through said method - Google Patents
Method for neutralizing iron scrap and/or steel scrap contaminated by radiation and use to storage vessel of iron and steel obtained through said methodInfo
- Publication number
- JPS6037000A JPS6037000A JP9888184A JP9888184A JPS6037000A JP S6037000 A JPS6037000 A JP S6037000A JP 9888184 A JP9888184 A JP 9888184A JP 9888184 A JP9888184 A JP 9888184A JP S6037000 A JPS6037000 A JP S6037000A
- Authority
- JP
- Japan
- Prior art keywords
- iron
- steel
- scrap
- melt
- radiation
- 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
Classifications
-
- 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
- G21F9/308—Processing by melting the waste
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Carbon Steel Or Casting Steel Manufacturing (AREA)
- Manufacture And Refinement Of Metals (AREA)
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】
本発明は、鉄／銅−溶融物用のスラッジ化剤の存在下で
スクラップを溶融することにより放射線で汚染された鉄
スクラツプおよび／又は鋼スクラツプを除毒するだめの
方法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention provides a method for detoxifying radioactive iron scrap and/or steel scrap by melting the scrap in the presence of an iron/copper melt sludge agent. Regarding the method.
工ＡＥＡＳＭ ２３４／１４におけるＪ、Ｈ＋Ｃａｖｅ
ｎｄｉｓｈ著「Ｔｒｅａｔｍｅｎｔ ｏｆ Ｍｅｔａｌ
ｌｉｃ Ｗａｓｔｅｓ ｂｙ Ｅｌ１ｍｓ’ｌｔｉｎｇ
（溶融による金に屑物の熱処理）」にょシ、既にウラン
弗素化合物、ネプツニウム、プルトニウムおよびテクネ
チウムで汚染された鋼スクラツプを先立って行われる化
学的洗滌の後溶融することによって除毒する方法が知ら
れている。J, H+Cave in Engineering AEASM 234/14
“Treatment of Metal” by ndish
lic Wastes by El1ms'lting
(Heat treatment of gold scraps by melting) It is already known how to detoxify steel scrap contaminated with uranium-fluoride compounds, neptunium, plutonium and technetium by melting it after a previous chemical cleaning. It is being
溶融物には珪藻土と石灰から成る混合物の形でスラッジ
化剤が添加さ昶、この場合ウラン、ネプツニウムおよび
プルトニウムが十分にスラッジ内に沈殿し、次いでこの
スラッジは分離される。この方法により、廃変物の除去
は再使用不能なスクラップ部分の容量が低減されるので
容易になる。更に、溶融物内に残留している僅かに放射
性の物質の再使用−が提案されている。A sludge agent in the form of a mixture of diatomaceous earth and lime is added to the melt so that uranium, neptunium and plutonium are sufficiently precipitated into the sludge, which is then separated. This method facilitates waste removal as the volume of non-reusable scrap parts is reduced. Furthermore, it has been proposed to reuse the slightly radioactive material remaining in the melt.
鉛の除毒を行うための方法も既に提案されている（ ０
ｅｒｒｅ’ ：ｐ、 Ｍｅｓｔｒｅ Ｅ、 ０Ｏｕｒｆ
；ａｕｌｌｌｌ Ｊｉ Ｌａｄｅｃｏｎｔａｍｉｎａｔ
ｉｏｎ ｄｕ ｐｌｏｍｐ、 Ｂｕｌｌｅｔｉｎ工ｎｆ
ｏｒ−ｍａｔｉｑｕｅｓ Ｅｌｃｉｅｎｔｉｆｉｃ ｅ
ｔ Ｔｅｃｈｎｉｑｕｅｓ （科学技術誌：鉛の除毒）
）６９巻Ｓ４９〜５８頁（１９６３）参照）。Methods for detoxifying lead have already been proposed (0
erre' :p, Mestre E, 0Ourf
;aullll Ji Ladecontaminat
ion du plomp, bulletin engineering nf
or-matiques
t Techniques (Science and Technology Magazine: Lead Detoxification) Vol. 69, pp. S49-58 (1963)).
公知方法では鉛−大抵鉛板の形でではあるが一実験室お
よび類似の装置内においてエネルギーに富む放射線を遮
蔽するのに使用される。In the known method, lead, usually in the form of lead plates, is used for shielding energetic radiation in laboratories and similar equipment.
材料費が高いことから、既に以前から汚染された鉛を再
使用することへの努力が払われて来た。Due to the high cost of materials, efforts have already been made to reuse contaminated lead.
停止している原子力発電所における危険排除を行う際、
炉心の領域から比較的強い活性の組成物が生成するが、
この組成物を最終貯蔵所に搬入するのに確実な遮蔽を行
う必要がある。更に、多量の汚染された鋼材部分を除毒
しなければならない。既に、これらの汚染された鋼材部
分を溶融し、これから遮蔽部材を造り、これを著しく放
射性の廃棄物の除金を行う際に使用することが提案され
ている（ （Ａｔｏｍθｎｅｒｇｉθ／Ｋｅｒｎｔｅｃ
ｈｎｉｋ ） ４１版（１９８２）２７９〜２８０参照
）。これにより、廃、棄物の容量の低減、したがづてま
た最終貯蔵所における貯蔵のだめの費用の著しい低減の
ための道および、廃棄物にとって有意義な使用のだめの
通が開かれた。When eliminating danger at a stopped nuclear power plant,
Relatively active compositions are produced from the core region, but
Reliable shielding is required to transport this composition to final storage. Furthermore, a large amount of contaminated steel parts must be detoxified. It has already been proposed that these contaminated steel parts be melted down and used to make shielding members for use in removing highly radioactive waste ((Atomθnergiθ/Kerntec
hnik) 41st edition (1982) 279-280). This opens the way for a reduction in the volume of waste, and thus also a significant reduction in the cost of storage bins in final storage, and a meaningful use of bins for the waste.
本発明は、例えば再処理装置から生成する表面が放射線
により汚染された鋼スクラツプにのみ関する。この場合
、大きな滑らかな面は迅速に除毒され得るが、他方壁の
凹み、角隅、割れ目、接続管および閉じられている管端
部の除毒は比較的太き表エネルギーおよび経費を要する
。The invention relates only to steel scrap whose surface is contaminated by radiation, for example from reprocessing equipment. In this case, large smooth surfaces can be detoxified quickly, whereas detoxification of wall depressions, corners, crevices, connecting pipes and closed pipe ends requires relatively large surface energy and expense. .
放射性による汚染は表面領域内においては指数の割合い
での深さ分布を、有しているので、従来の除毒処理に要
するエネルギーおよび経費が放射性の放射線のより以上
の低減に対する費用上不都合な状態に存在している点を
見出すことができる。鋼スクラツプはその際でもまだ残
存放射能を有している。放射性の廃棄物の量は相応する
法律上の規則によりクリアランスリミット（放射性廃棄
物と非活性の廃棄物間の制限値）を適用して得られる。Because radioactive contamination has an exponential rate of depth distribution within the surface area, the energy and expense required for conventional detoxification processes makes further reductions of radioactive radiation a cost disadvantage. You can find points that exist in . Steel scrap still has residual radioactivity. The amount of radioactive waste is determined by applying clearance limits (limit values between radioactive and inactive waste) according to the corresponding legal regulations.
残存放射能は一般に、鋼スクラツプをそのまま直かに利
用することを妨げる。このスクラップは僅かに放射性の
廃棄物として、最終貯蔵所内に入れることが可能である
程度に処理されるか或いは異論なくリサイクルできる程
度に除毒される。Residual radioactivity generally precludes direct use of steel scrap. This scrap is either treated as slightly radioactive waste to the extent that it can be placed in a final repository, or detoxified to the extent that it can be safely recycled.
本発明の根底をなす課題は、鉄スクラツプおよび／又は
鋼スクラツプを溶融除毒するための方法に関する。The problem underlying the invention relates to a method for melt detoxification of iron and/or steel scrap.
上記の課題は本発明によシ、附加的に不活性の同位元素
を溶融物中に存在している放射性要素に添加し、かつ溶
融処理工程を施すことによって解決される。The above problem is solved according to the invention by additionally adding an inert isotope to the radioactive element present in the melt and by subjecting it to a melt processing step.
本発明による除毒方法は、汚染された鋼或いは鉄の溶融
物および鋼或いは鉄の表面を汚染している放射性の元素
のスラッジのだめの冒頭に記載した様式の方法から出発
する。The detoxification method according to the invention starts from a process in the manner described at the outset of a contaminated steel or iron melt and a sludge pool of radioactive elements contaminating the steel or iron surface.
この公知の溶融冶金技術による処理にあって大力の放射
性元素のスラッジ化が行われる。即ち、放射性元素は金
属間化合物に移行し、この金属間化合物は基礎物質よシ
軽＜、シたがってスラッジ内で溶融物の表面上に集まる
。放射性の結合した元素を含むスラッジはその際スラッ
ジの表面から取去られ、最終貯蔵結合物に加工される。In this process using the known fusion metallurgy technique, a large amount of radioactive elements are converted into sludge. That is, the radioactive elements migrate into intermetallic compounds, which are lighter than the base material and therefore collect on the surface of the melt in the sludge. The sludge containing the radioactive bound elements is then removed from the surface of the sludge and processed into the final storage combination.
しかし、この公知の除毒方法にあっては、「除毒された
」鋼スクラツプの再使用にとっては問題があると思われ
る著しい存残放射能が未だ残留している。However, this known detoxification method still leaves significant residual radioactivity which may pose a problem for the reuse of "detoxified" steel scrap.
例えば高炉工程において使用される上記のスラッジ化剤
の成分は、例えば
０ａ０３５〜４０％ Ｔ、ＩＯ，ｆ％
５ｉ０２８〜４０％ Ｎａ２ＯＱ、１％Ａ１ｚＯｘ ５
〜１５％ Ｋ、０ ２％Ｍｇ０ ２〜１３％ ＦｅＯ１
％
Ｍｎ０ １０％
であシ、この場合１ｔの素鋼で３００〜８００ゆのスラ
ッジ化剤が使用される。For example, the components of the above-mentioned sludge forming agent used in the blast furnace process are, for example, 0a035-40% T, IO, f% 5i028-40% Na2OQ, 1%A1zOx 5
~15% K, 0 2% Mg0 2-13% FeO1
% Mn0 10%, in this case 300 to 800 yu of sludge forming agent is used for 1 ton of raw steel.
本発明による処置、即ち不活性の同位元素の添加によシ
、元素比溶解度に相応して元素の放射性同位元素が溶融
物から押出されスラッジ内に集る。とれによって残存放
射能の著しい低減が達せられ、したがって実際に等閑し
得る放射能を有する鋼溶融物が得られる。Due to the treatment according to the invention, ie the addition of inert isotopes, radioactive isotopes of the elements are forced out of the melt and collect in the sludge, depending on the specific solubility of the element. By stripping, a significant reduction in the residual radioactivity is achieved and a steel melt is thus obtained which has practically equivalent radioactivity.
核技術分野の設備の停止と補修から出る放射線により汚
染されたスクラップの量が極めて大きく、かつ地下の最
終貯蔵のために準備処理しなければならない容量に基い
て費用が多額なものとなるので、本発明による方法は著
しい進歩である。なぜなら、本発明による溶融除毒によ
シ最終貯蔵のだめの容量が大規模に節約できるからであ
る。溶融物から得られる素鋼はリサイクルされ、再使用
される。放射性のスラッジはする。Because the amount of radioactive scrap from the shutdown and repair of nuclear technology equipment is extremely large and the costs are high based on the volumes that have to be prepared for final underground storage, The method according to the invention is a significant advance. This is because melt detoxification according to the invention results in significant savings in final storage capacity. The raw steel obtained from the melt is recycled and reused. Radioactive sludge does.
なかんずく、本発明による方法には元素、即ちストロン
チウム、バリウム、セリウム、ユーロピウムおよびジル
コニウムが該轟する。セシウムとアンチモンは溶融工程
にあって蒸発し、廃ガスから炉出される。Among others, the elements strontium, barium, cerium, europium and zirconium are used in the process according to the invention. Cesium and antimony are vaporized during the melting process and removed from the waste gas.
本発明の他の有利なかつ合目的的な構成は、特許請求の
範囲第２項〜第５項に記載した。Other advantageous and expedient developments of the invention are specified in the claims 2 to 5.
上記のように放射性の元素もしくは核分裂物質を含んで
いる分離されたスラッジは、同様に既に上に述べたよう
に、最終貯蔵可能な生成物に加工され、特許請求の範囲
第５項に記載したように除毒された鉄或いは鋼から造ら
れた容器内に充填される。The separated sludge containing radioactive elements or fissile material as described above is likewise processed into a final storable product, as already mentioned above, and as defined in claim 5. It is packed in a container made from detoxified iron or steel.
Claims (1)
スクラップを溶融することによって放射線によって汚染
された鉄スクラツプおよび／又は鋼スクラツプを除毒す
るだめの方法において、附加的に不活性の同位元素を溶
融物中に存在している放射性元素に添加し、溶融工程を
施すことを特徴とする上記方法。 Ｚ 不活性の同位元素を溶融物に加える、前記特許請求
の範囲第１項に記載の方法。 五 不活性の同位元素を鉱物の形で添加する、前記特許
請求の範囲第１項或いは第２項に記載の方法。 ４、 元素であるストロンチウム、バリウム、セリウム
、ユーロピウムおよびジルコニウムの不活性の同位元素
を特徴する特許請求の範囲第１項から第３項までのうち
のいずれか一つに記載の方法。 ５、 鉄／鋼−溶融物のためのスラッジ化剤の存在下に
スクラップを溶融するととによって放射線によって汚染
された鉄スクラツプおよび／又は鋼スクラツプを除毒す
るための方法により、附加的に不活性の同位元素を溶融
物中に存在している放射性元素に添加し、溶融工程を施
すことによって得られた除毒源れた鉄および／又は鋼を
放射性の廃棄物を貯蔵するだめの容器を造るために使用
することを特徴とする、除毒された鉄および／又は鋼の
使用。Claims: 1. Iron/Steel - In a sump method for detoxifying iron scrap and/or steel scrap contaminated by radiation by melting the scrap in the presence of a sludge agent in the melt sump, A method as described above, characterized in that an inert isotope is additionally added to the radioactive element present in the melt and a melting step is carried out. 2. A method according to claim 1, wherein Z an inert isotope is added to the melt. 5. The method according to claim 1 or 2, wherein the inert isotope is added in the form of a mineral. 4. Process according to any one of claims 1 to 3, characterized in that it is an inert isotope of the elements strontium, barium, cerium, europium and zirconium. 5. Iron/steel - a method for detoxifying iron scrap and/or steel scrap contaminated by radiation by melting the scrap in the presence of a sludge agent for the melt and additionally inert isotopes are added to the radioactive elements present in the melt, and the detoxified iron and/or steel obtained by the melting process is used to create containers for storing radioactive waste. use of detoxified iron and/or steel, characterized in that it is used for
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19833318377 DE3318377C2 (en) | 1983-05-20 | 1983-05-20 | Process for the decontamination of radioactively contaminated iron and / or steel scrap |
| DE3318377.5 | 1983-05-20 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6037000A true JPS6037000A (en) | 1985-02-26 |
Family
ID=6199465
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP9888184A Pending JPS6037000A (en) | 1983-05-20 | 1984-05-18 | Method for neutralizing iron scrap and/or steel scrap contaminated by radiation and use to storage vessel of iron and steel obtained through said method |
Country Status (6)
| Country | Link |
|---|---|
| JP (1) | JPS6037000A (en) |
| BE (1) | BE899697A (en) |
| BR (1) | BR8402397A (en) |
| DE (1) | DE3318377C2 (en) |
| FR (1) | FR2546332B1 (en) |
| GB (1) | GB2141866B (en) |
Families Citing this family (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3527319A1 (en) * | 1985-07-31 | 1987-02-12 | Siempelkamp Gmbh & Co | USE OF RADIOACTIVE RESIDUES AS A BUILDING MATERIAL |
| DE3644396C1 (en) * | 1986-12-24 | 1988-02-11 | Martin Ganter | Process for decontamination of radioactive liquids |
| GB2266002B (en) * | 1992-04-10 | 1996-01-03 | Altra Consultants Limited | A method of removing radioactive material from metallic objects |
| GB2272566B (en) * | 1992-11-17 | 1996-01-24 | Clyde Shaw Ltd | Decontamination method |
| SE507554C2 (en) * | 1993-02-25 | 1998-06-22 | Siempelkamp Gmbh & Co | Ways to extract metals from radioactive contaminated iron scrap |
| DE4427179A1 (en) * | 1994-08-01 | 1996-02-08 | Siemens Ag | Process for recycling metal parts that are radioactively contaminated by uranium |
| FR2730091A1 (en) * | 1995-02-01 | 1996-08-02 | Commissariat Energie Atomique | DECONTAMINATION OF ZIRCALOY USING A SLAG BY A COLD CRUCIBLE MELTING OPERATION WITH CONTINUOUS LINGOT DRAWING |
| WO1996041348A1 (en) * | 1995-06-07 | 1996-12-19 | Molten Metal Technology, Inc. | Apparatus and method for reducing volume of radioactive waste |
| DE19543549A1 (en) * | 1995-11-22 | 1997-05-28 | Siemens Ag | Process for recycling contaminated metal parts |
| DE19546789A1 (en) * | 1995-12-14 | 1997-06-19 | Siemens Ag | Process for recycling contaminated metal parts |
| DE19547298A1 (en) * | 1995-12-18 | 1997-06-19 | Siemens Ag | Process for recycling contaminated metal parts |
| CN103805750A (en) * | 2012-11-08 | 2014-05-21 | 中国辐射防护研究院 | Fluxing agent used for smelting decontamination of uranium-contaminated carbon steel or stainless steel |
| CN103811091B (en) * | 2012-11-08 | 2016-10-12 | 中国辐射防护研究院 | High level uranium pollutes carbon steel or stainless steel melting decontamination technique |
| DE202018100057U1 (en) | 2018-01-05 | 2018-03-18 | Joachim Ferdyn | Mobile device for the treatment of nuclear contaminated body |
| EP3706140A1 (en) | 2019-03-06 | 2020-09-09 | Evekinger Rohr- und Profilwerke GmbH | Device and method for decontaminating a wall surface of in particular a hollow body |
| DE102019118596B3 (en) * | 2019-07-09 | 2020-11-19 | Evekinger Rohr- Und Profilwerke Gmbh | Device for processing a functional element and a guide intended for use in the device |
-
1983
- 1983-05-20 DE DE19833318377 patent/DE3318377C2/en not_active Expired
-
1984
- 1984-05-03 GB GB08411358A patent/GB2141866B/en not_active Expired
- 1984-05-18 JP JP9888184A patent/JPS6037000A/en active Pending
- 1984-05-18 FR FR8407715A patent/FR2546332B1/en not_active Expired
- 1984-05-18 BR BR8402397A patent/BR8402397A/en unknown
- 1984-05-18 BE BE0/212960A patent/BE899697A/en not_active IP Right Cessation
Also Published As
| Publication number | Publication date |
|---|---|
| BR8402397A (en) | 1985-04-02 |
| GB2141866A (en) | 1985-01-03 |
| DE3318377A1 (en) | 1984-11-22 |
| BE899697A (en) | 1984-09-17 |
| GB8411358D0 (en) | 1984-06-27 |
| DE3318377C2 (en) | 1986-05-15 |
| FR2546332B1 (en) | 1987-06-12 |
| GB2141866B (en) | 1987-05-13 |
| FR2546332A1 (en) | 1984-11-23 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JPS6037000A (en) | Method for neutralizing iron scrap and/or steel scrap contaminated by radiation and use to storage vessel of iron and steel obtained through said method | |
| US8754282B2 (en) | Methods of consolidating radioactive containing materials by hot isostatic pressing | |
| US3463635A (en) | Recovery of mercury from nuclear fuel reprocessing wastes | |
| US5998689A (en) | Method for recycling contaminated metal parts | |
| KR102497975B1 (en) | A treatment method for concentrated radioactive waste solidified by using paraffin wax and stored in the interim storage on the nuclear power plants | |
| GB2266002A (en) | A method of removing radioactive material from metallic objects | |
| JPS59126297A (en) | Method of processing incombustible solid waste | |
| RU2189653C1 (en) | Method for handling limited-use metal wastes | |
| US5732366A (en) | Method of reprocessing metal parts radioactively contaminated with uranium | |
| Klein et al. | Management routes for materials arising from the decommissioning of a PWR reactor | |
| JP2004239693A (en) | Method for melting treatment of radioactive contaminated metal | |
| US20030041874A1 (en) | Method of treating contaminated HEPA filter media in pulp process | |
| JPS62898A (en) | Method of reprocessing spent nuclear fuel | |
| US5033533A (en) | Method for producing a container for contaminated metal waste, and a container produced by this method | |
| Harmon | Trends in actinide processing at Hanford | |
| Kikuchi et al. | Developing Technologies for Nuclear Fuel Cycles | |
| Menon et al. | Melting of Low-Level Contaminated Steels | |
| Cavendish | Treatment of metallic wastes by smelting | |
| Haghighi et al. | Waste Stream Generated and Waste Disposal Plans for Molten Salt Reactor Experiment at Oak Ridge National Laboratory | |
| Lin | Characteristics of radioactive waste streams generated in HTGR fuel reprocessing | |
| JPS59204000A (en) | Method of processing radioactive solid waste | |
| Höhlein | TREATMENT OF NUCLEAR WASTES | |
| JPS6412360B2 (en) | ||
| GB2508010A (en) | Treatment of Radioactive Material | |
| RU1831879C (en) | Method for utilization of wastes of ferrous alloys contaminated with radionuclides and unit for its embodiment |