JPH0664192B2 - Equipment for melting and solidifying radioactive waste - Google Patents

Equipment for melting and solidifying radioactive waste

Info

Publication number
JPH0664192B2
JPH0664192B2 JP60049367A JP4936785A JPH0664192B2 JP H0664192 B2 JPH0664192 B2 JP H0664192B2 JP 60049367 A JP60049367 A JP 60049367A JP 4936785 A JP4936785 A JP 4936785A JP H0664192 B2 JPH0664192 B2 JP H0664192B2
Authority
JP
Japan
Prior art keywords
waste
melting
container
radioactive waste
solidifying
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 - Lifetime
Application number
JP60049367A
Other languages
Japanese (ja)
Other versions
JPS61209399A (en
Inventor
修一 吉田
英治 澤田
秋夫 神野
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
Original Assignee
NGK Insulators Ltd
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 filed Critical NGK Insulators Ltd
Priority to JP60049367A priority Critical patent/JPH0664192B2/en
Priority to US06/834,764 priority patent/US4816228A/en
Priority to EP86301822A priority patent/EP0196809B1/en
Priority to DE8686301822T priority patent/DE3664015D1/en
Priority to KR1019860001860A priority patent/KR900007748B1/en
Publication of JPS61209399A publication Critical patent/JPS61209399A/en
Publication of JPH0664192B2 publication Critical patent/JPH0664192B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/308Processing by melting the waste
    • CCHEMISTRY; METALLURGY
    • C03GLASS; MINERAL OR SLAG WOOL
    • C03BMANUFACTURE, SHAPING, OR SUPPLEMENTARY PROCESSES
    • C03B5/00Melting in furnaces; Furnaces so far as specially adapted for glass manufacture
    • C03B5/02Melting in furnaces; Furnaces so far as specially adapted for glass manufacture in electric furnaces, e.g. by dielectric heating
    • C03B5/021Melting in furnaces; Furnaces so far as specially adapted for glass manufacture in electric furnaces, e.g. by dielectric heating by induction heating
    • CCHEMISTRY; METALLURGY
    • C03GLASS; MINERAL OR SLAG WOOL
    • C03BMANUFACTURE, SHAPING, OR SUPPLEMENTARY PROCESSES
    • C03B5/00Melting in furnaces; Furnaces so far as specially adapted for glass manufacture
    • C03B5/16Special features of the melting process; Auxiliary means specially adapted for glass-melting furnaces
    • C03B5/42Details of construction of furnace walls, e.g. to prevent corrosion; Use of materials for furnace walls
    • C03B5/43Use of materials for furnace walls, e.g. fire-bricks

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)
  • Gasification And Melting Of Waste (AREA)
  • Furnace Details (AREA)

Description

【発明の詳細な説明】 (産業上の利用分野) 本発明は、放射性廃棄物を溶融固化する装置に関するも
ので、更に詳しくは、1300℃以上の高温度においても使
用可能な溶融固化装置に関するものである。
TECHNICAL FIELD The present invention relates to an apparatus for melting and solidifying radioactive waste, and more specifically to a melting and solidifying apparatus that can be used even at a high temperature of 1300 ° C. or higher. Is.

(従来の技術) 従来原子力発電所等の放射性物質取扱施設から発生する
放射能によって汚染された廃棄物のうち可燃性のもの
は、一般的には焼却処理されその焼却灰はドラム罐等に
充填されて施設内の適当な場所に貯蔵されているのが普
通である。しかしながらこれら焼却灰は、粉粒状である
ため、焼却灰を充填したドラム罐を輸送または貯蔵する
にあたっては焼却灰の安定化、減容処理を施すことが望
ましく、その処理法がいろいろ研究されている。
(Prior art) Combustible waste that has been contaminated by radioactivity generated from conventional radioactive material handling facilities such as nuclear power plants is generally incinerated, and the incinerated ash is filled in drum cans. It is usually stored in an appropriate place in the facility. However, since the incinerated ash is in the form of powder, it is desirable to stabilize and reduce the volume of the incinerated ash when transporting or storing the drum can filled with the incinerated ash, and various treatment methods have been studied. .

最近提案されているこれら放射性廃棄物の処理法として
は、放射性廃棄物又は焼却灰をセメントで固化する第1
の方法、あるいは放射性廃棄物又は焼却灰にアスファル
ト、プラスチックス等を混合して固化する第2の方法が
よく知られている。さらに、最近になって放射性廃棄物
または焼却灰を高温度で加熱溶融固化する第3の方法が
提案されている。
The most recently proposed method for treating these radioactive wastes is to solidify the radioactive wastes or incinerated ash with cement.
Or the second method of mixing radioactive waste or incineration ash with asphalt, plastics and the like to solidify. Furthermore, a third method has recently been proposed in which radioactive waste or incineration ash is heated and melted and solidified at a high temperature.

(発明が解決しようとする問題点) しかしながら、第1の方法であるセメント固化法におい
ては、廃棄物または灰とセメントを混合して、安定した
密度、強度等をもつ固化体を得るには、灰等とセメント
の重量割合を灰等を1に対してセメント4以上とする必
要があり、このため固化体容積が灰等の容積よりも増大
し増容となってしまう欠点があった。また、第2の方法
であるアスファルトおよびプラスチック固化法において
は、廃棄物または焼却灰中の金属片の除去、粉体化等の
前処理が必要であり、設備が複雑かつ大型となる欠点が
あった。
(Problems to be Solved by the Invention) However, in the cement solidification method, which is the first method, in order to obtain a solidified body having stable density, strength, etc. by mixing waste or ash with cement, It is necessary to set the weight ratio of ash or the like to cement to be 4 or more of cement relative to 1 of ash or the like, which causes a problem that the volume of the solidified body is increased to increase the volume of the ash or the like. In addition, the second method, the asphalt and plastic solidification method, requires a pretreatment such as removal of metal pieces from waste or incinerated ash and pulverization, which has a drawback that equipment is complicated and large. It was

さらに、第3の方法である加熱溶融固化法においては、
上述した第1および第2の方法で生じる欠点を有効に除
去できるが、廃棄物または焼却灰を高温度で溶融するた
め電磁誘導によって金属容器を加熱して高温度を達成し
ており、1000〜1200℃の温度での使用が限界でありそれ
以上の高温で溶融する廃棄物等の溶融処理ができない欠
点があった。
Furthermore, in the heating, melting and solidifying method, which is the third method,
Although the drawbacks caused by the first and second methods described above can be effectively removed, the metal container is heated by electromagnetic induction to attain a high temperature in order to melt waste or incineration ash at a high temperature, There is a drawback that the use at a temperature of 1200 ° C is limited and the melting treatment of wastes that melt at higher temperatures cannot be performed.

本発明の目的は上述した不具合を解消して、1300〜1600
℃の高温においても放射性廃棄物または焼却灰を溶融す
ることができ、輸送、貯蔵に適した安定な減容した固化
体に転換することができる溶融固化装置を提供しようと
するものである。
The object of the present invention is to eliminate the above-mentioned problems, and
An object of the present invention is to provide a melting and solidifying apparatus capable of melting radioactive waste or incinerated ash even at a high temperature of ° C and converting it into a stable solidified body having a reduced volume suitable for transportation and storage.

(問題点を解決するための手段) 本発明の放射性廃棄物の溶融固化装置は、放射性廃棄物
の溶融固化装置であって、昇降可能な底蓋によって底部
を閉鎖された炉本体と、前記炉本体の側壁の外周部に設
けられた電磁誘導加熱コイルと、前記炉本体の内部の底
蓋上に載置され、電磁誘導加熱コイルによって高温に電
磁誘導加熱されるC-SiC系またはC-Al2O3系セラミック発
熱体よりなる廃棄物収納容器と、炉本体の上蓋に設けら
れた炉内排ガス排出口と、前記廃棄物収納容器中へ放射
性廃棄物を投入する廃棄物供給口とを具えることを特徴
とするものである。
(Means for Solving Problems) A melting and solidifying apparatus for radioactive waste according to the present invention is a melting and solidifying apparatus for radioactive waste, which comprises a furnace main body whose bottom is closed by a vertically movable bottom lid, and the furnace. An electromagnetic induction heating coil provided on the outer peripheral portion of the side wall of the main body, and a C-SiC system or C-Al that is placed on the bottom lid inside the furnace main body and is heated by the electromagnetic induction heating coil to a high temperature. 2 O 3 -based ceramic heating element, a waste container, a furnace exhaust gas outlet provided on the upper lid of the furnace body, and a waste supply port for introducing radioactive waste into the waste container. It is characterized by getting.

(作用) 本発明では、廃棄物収納容器をC-SiC系、C-A
系等のセラミック発熱体で作成しているので、容器を加
熱する特別な発熱体を用いずに容器自体が誘導加熱によ
って効果的に発熱する。また、容器及び発熱体が特別の
セラミック材で形成されているので、1300〜1600℃の高
温度領域でも安定して使用できるよう構成されている。
さらに、酸素含有ガスを供給する実施例では、廃棄物の
焼却と溶融固化とを同時に実施することができるよう構
成されている。
(Operation) In the present invention, the waste storage container is made of C-SiC system, C-A 2 O 3
Since it is made of a ceramic heating element such as a system, the container itself effectively generates heat by induction heating without using a special heating element for heating the container. Further, since the container and the heating element are made of a special ceramic material, the container and the heating element can be stably used even in a high temperature range of 1300 to 1600 ° C.
Further, in the embodiment in which the oxygen-containing gas is supplied, the incineration and the melting and solidification of the waste can be simultaneously performed.

(実施例) 以下図面を参照して本発明を詳細に説明する。(Example) Hereinafter, the present invention will be described in detail with reference to the drawings.

第1図は本発明の溶融固化装置の一実施例を示す断面図
である。第1図において、基礎に立設した支枠1により
支持された密閉容器状の炉本体2は、非金属材料、例え
ば石英質製の円筒状の側壁3と、これに被着された金属
製の蓋部4とから成る。基礎に立設したガイド5によっ
て昇降自在に案内され図示しないモーター等の駆動装置
により昇降駆動される昇降台6には、炉本体2の底部を
開放自在に閉鎖する底蓋7を固着する。側壁3の外周部
には誘導加熱コイル8を取付ける。この誘導加熱コイル
8はカバー9内に収められ、空冷あるいは水冷などの公
知の冷却方法によって冷却される。一方、炉本体2の側
壁3の内側にはアスベスト、キャスタブル等の断熱材よ
り成る円筒状の断熱壁11を設ける。断熱壁11の上端部に
は孔12をそなえた断熱蓋13が被着され、この断熱蓋13は
炉本体2または支枠1に固定支持されている。
FIG. 1 is a sectional view showing an embodiment of the melting and solidifying apparatus of the present invention. In FIG. 1, a closed vessel-shaped furnace body 2 supported by a supporting frame 1 erected on a foundation comprises a cylindrical side wall 3 made of a non-metallic material, for example, silica, and a metallic side wall adhered thereto. And the lid portion 4 of the. A bottom cover 7 for opening and closing the bottom of the furnace main body 2 is fixed to an elevating table 6 which is guided up and down by a guide 5 standing on the foundation and driven up and down by a driving device such as a motor (not shown). An induction heating coil 8 is attached to the outer peripheral portion of the side wall 3. The induction heating coil 8 is housed in the cover 9 and cooled by a known cooling method such as air cooling or water cooling. On the other hand, a cylindrical heat insulating wall 11 made of a heat insulating material such as asbestos or castable is provided inside the side wall 3 of the furnace body 2. A heat insulating lid 13 having a hole 12 is attached to the upper end of the heat insulating wall 11, and the heat insulating lid 13 is fixedly supported by the furnace body 2 or the support frame 1.

また、底蓋7に固設した断熱材などの非金属より成る支
台14上には、セラミック発熱体、好ましくはC-SiC系ま
たはC-A系セラミックスより成る廃棄物収納容
器15を載置する。容器15は底蓋7およびこれと一体の支
台14と共に昇降駆動され、断熱壁11内に下方から挿脱自
在に構成されている。炉本体2の上部には排ガス排出口
16を設けて、溶融時の排ガス等を断熱蓋13に設けた孔12
を介して外部へ導く構成をとっている。また、炉本体2
の蓋部4には、廃棄物収納容器15内へ放射性廃棄物等を
供給する廃棄物供給口17、および必要に応じ容器15中へ
供給される廃棄物または焼却灰中の未燃分を燃焼させる
に必要な酸素含有ガスを供給する酸素供給管18が設けら
れ、さらに容器15内の溶融状態を検知する放射温度計、
液面計、モニタTV等の検知装置19をそれぞれ蓋部4を貫
通して取付ける。
Further, a waste storage container 15 made of a ceramic heating element, preferably C-SiC or C-A 2 O 3 ceramics is mounted on a support 14 made of a non-metal such as a heat insulating material fixed to the bottom cover 7. To place. The container 15 is driven up and down together with the bottom cover 7 and the abutment 14 integrated therewith, and is configured to be inserted into and removed from the heat insulating wall 11 from below. Exhaust gas exhaust port at the top of the furnace body 2
A hole 12 that is provided with 16 and provided with a heat insulating lid 13 for exhaust gas at the time of melting
It is configured to be guided to the outside via. Also, the furnace body 2
In the lid part 4 of the waste container 17, a waste supply port 17 for supplying radioactive waste or the like into the waste container 15 and, if necessary, the waste material supplied into the container 15 or unburned matter in the incinerated ash is burned. An oxygen supply pipe 18 is provided for supplying an oxygen-containing gas necessary for the radiation thermometer to detect a molten state in the container 15,
A detection device 19 such as a liquid level gauge and a monitor TV is attached through the lid 4.

上記構成を有する放射性廃棄物の溶融固化装置20におい
ては、誘導加熱コイル8に通電するとセラミック発熱体
より成る廃棄物収納容器15自体が直接加熱されるため、
1300〜1600℃の高温域で廃棄物を溶融させることができ
る。容器15内の溶融物が所定の量になったら、炉本体2
を自然放冷などで冷却し、溶融物が容器15内で固化して
容器15内に固定化されたら、昇降台6を降下させ容器15
を支台14上から取去って、新たな容器15を支台14上に載
置し、以下上記と同様な工程を繰返す。
In the radioactive waste melting and solidifying apparatus 20 having the above configuration, when the induction heating coil 8 is energized, the waste storage container 15 itself made of a ceramic heating element is directly heated.
The waste can be melted in the high temperature range of 1300 to 1600 ℃. When the melt in the container 15 reaches a predetermined amount, the furnace body 2
When the melt is solidified in the container 15 and fixed in the container 15, the elevating platform 6 is lowered to cool the container 15 by natural cooling.
Is removed from the abutment 14, a new container 15 is placed on the abutment 14, and the same steps as above are repeated.

第2図は本発明の溶融固化装置の他の実施例を示す要部
断面図であり、第1図に示す実施例と同一の部分には同
一の符号を付しその説明を省略する。本実施例では、廃
棄物収納容器15における誘導加熱の効率をさらに良好に
するため、セラミック発熱体よりなる廃棄物収納容器15
中に棒状のセラミック発熱体よりなる内部加熱体21を挿
入できるよう、2本の内部加熱体21を断熱蓋13に設置し
ている。上記構造によれば、誘導加熱時の電磁波が内部
加熱体21にも作用してより短時間で1300〜1600℃の温度
を達成することができる。
FIG. 2 is a cross-sectional view of essential parts showing another embodiment of the melting and solidifying apparatus of the present invention. The same parts as those in the embodiment shown in FIG. 1 are designated by the same reference numerals and the description thereof will be omitted. In this embodiment, in order to further improve the efficiency of induction heating in the waste container 15, the waste container 15 made of a ceramic heating element is used.
Two internal heating elements 21 are installed on the heat insulating lid 13 so that the internal heating element 21 made of a rod-shaped ceramic heating element can be inserted therein. According to the above structure, the electromagnetic wave at the time of induction heating also acts on the internal heating body 21, and the temperature of 1300 to 1600 ° C. can be achieved in a shorter time.

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、炉本体2
が断熱性に富む場合は断熱壁11および断熱蓋13を省略し
てもよい。
The present invention is not limited to the above-described embodiments, but various modifications and changes can be made. For example, the furnace body 2
If the heat insulating property is high, the heat insulating wall 11 and the heat insulating lid 13 may be omitted.

(発明の効果) 以上詳細に説明したところから明らかなように、本発明
の放射性廃棄物の溶融固化装置によれば、廃棄物収納容
器をセラミック発熱体により構成したため1300〜1600℃
の高温度でも安心して使用でき、従来1300℃以上の温度
で溶融処理することが不可能であった放射性廃棄物を溶
融処理することができる。また、廃棄物収納容器自身が
加熱されるので、容器を加熱する特別な発熱体が不要と
なり、装置自体の構成を簡単にすることができる。さら
に、溶融固化法を採用しているため、放射性廃棄物を安
定確実に減容化処理できる。
(Effect of the invention) As is clear from the above description in detail, according to the apparatus for melting and solidifying radioactive waste of the present invention, the waste container is composed of the ceramic heating element, and the temperature is 1300 to 1600 ° C.
It can be used with confidence even at high temperatures, and can process radioactive waste that could not be melt processed at temperatures above 1300 ° C. Moreover, since the waste container itself is heated, a special heating element for heating the container is not required, and the structure of the apparatus itself can be simplified. Furthermore, since the melting and solidification method is adopted, radioactive waste can be volume-reduced reliably and reliably.

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

第1図は本発明の溶融固化装置の一実施例を示す断面
図、 第2図は本発明の溶融固化装置の他の実施例を示す要部
断面図である。 2……炉本体、6……昇降台 7……底蓋、8……誘導加熱コイル 15……廃棄物収納容器、16……排ガス排出口 17……廃棄物供給口、18……酸素供給管 19……検知装置、20……溶融固化装置 21……内部加熱体
FIG. 1 is a sectional view showing an embodiment of the melting and solidifying apparatus of the present invention, and FIG. 2 is a sectional view of an essential part showing another embodiment of the melting and solidifying apparatus of the present invention. 2 ... Furnace body, 6 ... Lifting platform 7 ... Bottom lid, 8 ... Induction heating coil 15 ... Waste container, 16 ... Exhaust gas outlet 17 ... Waste supply port, 18 ... Oxygen supply Tube 19 …… Detecting device, 20 …… Melting and solidifying device 21 …… Internal heating element

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】放射性廃棄物の溶融固化装置であって、昇
降可能な底蓋によって底部を閉鎖された炉本体と、前記
炉本体の側壁の外周部に設けられた電磁誘導加熱コイル
と、前記炉本体の内部の底蓋上に載置され、電磁誘導加
熱コイルによって高温に電磁誘導加熱されるC-SiC系ま
たはC-Al2O3系セラミック発熱体よりなる廃棄物収納容
器と、炉本体の上蓋に設けられた炉内排ガス排出口と、
前記廃棄物収納容器中へ放射性廃棄物を投入する廃棄物
供給口とを具えることを特徴とする放射性廃棄物の溶融
固化装置。
1. A device for melting and solidifying radioactive waste, comprising a furnace main body whose bottom is closed by a vertically movable bottom lid, an electromagnetic induction heating coil provided on an outer peripheral portion of a side wall of the furnace main body, A waste storage container made of a C-SiC or C-Al 2 O 3 ceramic heating element that is placed on the bottom lid inside the furnace body and heated to high temperature by an electromagnetic induction heating coil. Exhaust gas exhaust port provided in the upper lid of the
A melting and solidifying device for radioactive waste, comprising: a waste supply port for introducing the radioactive waste into the waste container.
JP60049367A 1985-03-14 1985-03-14 Equipment for melting and solidifying radioactive waste Expired - Lifetime JPH0664192B2 (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
JP60049367A JPH0664192B2 (en) 1985-03-14 1985-03-14 Equipment for melting and solidifying radioactive waste
US06/834,764 US4816228A (en) 1985-03-14 1986-02-28 Apparatus for melting waste
EP86301822A EP0196809B1 (en) 1985-03-14 1986-03-13 Apparatus for melting waste
DE8686301822T DE3664015D1 (en) 1985-03-14 1986-03-13 Apparatus for melting waste
KR1019860001860A KR900007748B1 (en) 1985-03-14 1986-03-14 Apparatus for melting waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60049367A JPH0664192B2 (en) 1985-03-14 1985-03-14 Equipment for melting and solidifying radioactive waste

Publications (2)

Publication Number Publication Date
JPS61209399A JPS61209399A (en) 1986-09-17
JPH0664192B2 true JPH0664192B2 (en) 1994-08-22

Family

ID=12829045

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60049367A Expired - Lifetime JPH0664192B2 (en) 1985-03-14 1985-03-14 Equipment for melting and solidifying radioactive waste

Country Status (2)

Country Link
JP (1) JPH0664192B2 (en)
KR (1) KR900007748B1 (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2505881B2 (en) * 1989-05-12 1996-06-12 日本碍子株式会社 Equipment for melting radioactive waste
JP4713892B2 (en) * 2005-01-25 2011-06-29 新日鉄マテリアルズ株式会社 Crucible for refining silicon slag
JP5973157B2 (en) * 2011-12-08 2016-08-23 日本碍子株式会社 Treatment method for radioactive cesium contaminants
JP2013181858A (en) * 2012-03-02 2013-09-12 Tadashi Matsui Method for treating radioactive contaminant

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5331807B2 (en) * 1971-09-10 1978-09-05
JPS6019478B2 (en) * 1978-07-06 1985-05-16 株式会社 東芝 Vitrification method and vitrification equipment for radioactive waste
JPS5927491A (en) * 1982-08-05 1984-02-13 特殊電気工業株式会社 High frequency heat treating mechanism
JPS6038700A (en) * 1983-08-10 1985-02-28 東京電力株式会社 Method of melting and solidifying radioactive waste incinerated ash
JPH0231840B2 (en) * 1983-08-10 1990-07-17 Tokyo Denryoku Kk HOSHASEIHAIKIBUTSUSHOKYAKUBAINOYOJUKOKASOCHI

Also Published As

Publication number Publication date
KR860007679A (en) 1986-10-15
JPS61209399A (en) 1986-09-17
KR900007748B1 (en) 1990-10-19

Similar Documents

Publication Publication Date Title
US4816228A (en) Apparatus for melting waste
US5750822A (en) Processing of solid mixed waste containing radioactive and hazardous materials
JP2013525745A (en) Microwave enhanced system for pyrolysis and vitrification of radioactive waste
US4581163A (en) Method for conditioning weakly to medium-active wastes
JPS5990100A (en) Wrapping and higher density of granular substance
US7429239B2 (en) Methods for melting of materials to be treated
JPS6216399B2 (en)
KR900000326B1 (en) Method and device melting and solidifying radioactive waste
JPH0664192B2 (en) Equipment for melting and solidifying radioactive waste
JP2908584B2 (en) Radioactive waste melting equipment
JPS60186800A (en) Method and device for incinerating and solidifying radioactive waste
JP3073852B2 (en) Radioactive waste melting equipment
JPS6038698A (en) Device for melting and solidifying radioactive waste incinerated ash
JPH0668557B2 (en) Continuous waste melting device
JP3073851B2 (en) Waste incineration melting treatment device and incineration melting treatment method
JP3096184B2 (en) Waste melting method
JPH0530517B2 (en)
KR910003290B1 (en) Apparatus for melting waste
JP2002341092A (en) Miscellaneous solid waste volume reduction method and high frequency induction furnace for miscellaneous solid waste fusion
CA2498404C (en) Apparatus and method for vitrification of contaminated soil or waste
JPH0450558B2 (en)
JPH10319191A (en) Method for processing sealing end crop of spent nuclear fuel
JPH0629760Y2 (en) Storage device for solidified packages
RU2070307C1 (en) Plasma shaft furnace for processing the radioactive wastes
JPS63163199A (en) Melting solidifying processing device for radioactive waste

Legal Events

Date Code Title Description
EXPY Cancellation because of completion of term