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JP2966349B2 - Elemental separation method from mixed melt of high-level radioactive waste and glass raw material - Google Patents

Elemental separation method from mixed melt of high-level radioactive waste and glass raw material

Info

Publication number
JP2966349B2
JP2966349B2 JP19731696A JP19731696A JP2966349B2 JP 2966349 B2 JP2966349 B2 JP 2966349B2 JP 19731696 A JP19731696 A JP 19731696A JP 19731696 A JP19731696 A JP 19731696A JP 2966349 B2 JP2966349 B2 JP 2966349B2
Authority
JP
Japan
Prior art keywords
mixed melt
waste
raw material
glass raw
radioactive waste
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
JP19731696A
Other languages
Japanese (ja)
Other versions
JPH1039094A (en
Inventor
雅之 米谷
行生 花本
寛 五十嵐
和廣 河村
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.)
KAKUNENRYO SAIKURU KAIHATSU KIKO
Original Assignee
KAKUNENRYO SAIKURU KAIHATSU KIKO
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.)
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Application filed by KAKUNENRYO SAIKURU KAIHATSU KIKO filed Critical KAKUNENRYO SAIKURU KAIHATSU KIKO
Priority to JP19731696A priority Critical patent/JP2966349B2/en
Publication of JPH1039094A publication Critical patent/JPH1039094A/en
Application granted granted Critical
Publication of JP2966349B2 publication Critical patent/JP2966349B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】この発明は、使用済核燃料の
再処理工程から発生する高レベル放射性廃棄物から、有
用元素等の種々の元素を分離する技術に関し、更に詳し
くは、溶融炉内で高レベル放射性廃棄物をガラス原料と
混合溶融してガラス固化処理するに際して、溶融炉内の
混合溶融物から廃棄物中に含まれる種々の元素を分離す
る方法に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a technique for separating various elements such as useful elements from high-level radioactive waste generated in a reprocessing process of spent nuclear fuel, and more particularly, to a technique for separating high-level radioactive waste in a melting furnace. BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for separating various elements contained in waste from a mixed melt in a melting furnace when mixing and melting a level radioactive waste with a glass raw material and performing vitrification treatment.

【0002】[0002]

【従来の技術】使用済核燃料の再処理工程から排出され
る高レベル放射性廃液のごとき廃棄物(以下、高レベル
廃棄物という)に含まれる核分裂生成物、アクチニド元
素、腐食生成物等(以下、廃棄物成分という)は、処
理、貯蔵、処分の観点から、安定な形態に固定化するた
め、ガラス原料と共に高温で溶融し、高レベル廃棄物の
ガラス固化体とされる。すなわち、一対の電極を内部に
具備する溶融炉内に高レベル廃棄物とガラス原料とを投
入し、電極に交流電流を流すことにより、電極間の高レ
ベル廃棄物とガラス原料とを直接通電加熱(ジュール熱
による自己加熱)して混合溶融する。次いで混合溶融物
を溶融炉から取り出し、冷却してガラス固化体とされ
る。
2. Description of the Related Art Fission products, actinide elements, corrosion products, etc. (hereinafter, referred to as high-level waste) contained in wastes such as high-level radioactive liquid waste discharged from a reprocessing process of spent nuclear fuel (hereinafter, referred to as high-level waste) The waste component) is melted at a high temperature together with the glass raw material in order to fix it in a stable form from the viewpoint of treatment, storage and disposal, and is turned into a vitrified high-level waste. That is, a high-level waste and a glass raw material are charged into a melting furnace having a pair of electrodes therein, and an alternating current is applied to the electrodes, so that the high-level waste and the glass raw material between the electrodes are directly energized and heated. (Self-heating by Joule heat) to mix and fuse. Next, the mixed melt is taken out of the melting furnace and cooled to be a vitrified body.

【0003】しかしながら、高レベル廃棄物中には種々
の元素が含まれており、ガラス固化処理前に、再利用可
能な元素を高レベル廃棄物から分離することは、資源の
有効利用となる。高レベル廃棄物中の廃棄物成分から有
用元素を分離する方法としては、抽出溶媒と高レベル廃
棄物とを接触させて溶媒中に目的とする廃棄物成分を選
択的に抽出して分離する溶媒抽出法や、アルカリ金属や
アルカリ土類金属のフッ化物や塩化物等の溶融塩中への
廃棄物成分元素の溶解度の差を利用して目的とする元素
を分離する溶融塩電解法等が提案、研究されている。
[0003] However, various elements are contained in high-level waste, and separating reusable elements from high-level waste before vitrification treatment is an effective use of resources. As a method of separating useful elements from waste components in high-level waste, a solvent that selectively extracts a desired waste component in a solvent by contacting an extraction solvent with high-level waste and separating the solvent is used. Proposal of extraction method, molten salt electrolysis method, etc., which separates the target element using the difference in solubility of waste component elements in molten salts such as fluorides and chlorides of alkali metals and alkaline earth metals Has been studied.

【0004】[0004]

【発明が解決しようとする課題】上記のような分離方法
で高レベル廃棄物から各種の元素を分離した後の廃棄物
は、従来と同様にガラス原料と混合溶融されてガラス固
化体とされる。そのため、標準的なガラス固化プロセス
に上記の元素分離方法が付加されることになり、ガラス
固化処理プロセス全体を複雑にし、ガラス固化処理プロ
セスに関わる設計、製作費用を増加させることになる。
さらには、抽出溶媒や溶融塩を用いる元素分離方法で
は、抽出溶媒や溶融塩そのものが放射性廃棄物(二次廃
棄物)として発生し、標準的なガラス固化プロセスに比
べて、二次廃棄物発生による放射性廃棄物処理処分の管
理負担が多大になるという問題が生ずる。
The waste after separating various elements from the high-level waste by the above-mentioned separation method is mixed and melted with a glass raw material to form a vitrified body as in the conventional case. . Therefore, the element separation method described above is added to the standard vitrification process, which complicates the entire vitrification process and increases design and manufacturing costs related to the vitrification process.
Furthermore, in the element separation method using an extraction solvent or a molten salt, the extraction solvent or the molten salt itself is generated as radioactive waste (secondary waste), and the amount of secondary waste generated is smaller than in a standard vitrification process. A problem arises in that the management burden of the radioactive waste treatment and disposal due to is large.

【0005】そこでこの発明の目的は、高レベル廃棄物
から種々の元素を分離するに際して、抽出溶媒や溶融塩
を使用する必要がなく、従って二次廃棄物の発生量を少
なくすることができる方法を提供することである。
Accordingly, an object of the present invention is to provide a method for separating various elements from high-level waste without using an extraction solvent or a molten salt, thereby reducing the amount of secondary waste generated. It is to provide.

【0006】[0006]

【課題を解決するための手段】すなわちこの発明の第1
の実施態様は、一対の電極を内部に具備する溶融炉内に
高レベル廃棄物とガラス原料とを投入し、該電極に交流
電流を通電することにより該電極間の高レベル廃棄物と
ガラス原料とを直接通電加熱して混合溶融した後、該混
合溶融物を溶融炉から取り出して冷却しガラス固化体と
することからなる高レベル放射性廃棄物の固化処理に際
して、該溶融炉内の混合溶融物に該電極を介して直流電
流を通電して電気分解を行い、この電気分解により酸化
または還元される混合溶融物中の元素を該電極表面また
は該混合溶融物中に析出させることを特徴とする高レベ
ル放射性廃棄物とガラス原料との混合溶融物から元素を
分離する方法である。
That is, the first aspect of the present invention.
In the embodiment, the high-level waste and the glass raw material are charged into a melting furnace having a pair of electrodes therein, and an alternating current is applied to the electrodes, whereby the high-level waste and the glass raw material between the electrodes are supplied. Is heated and directly mixed to melt, and then the mixed melt is taken out of the melting furnace and cooled to form a vitrified material. A DC current is passed through the electrode to perform electrolysis, and the elements in the mixed melt that are oxidized or reduced by the electrolysis are deposited on the electrode surface or the mixed melt. This is a method for separating elements from a mixed melt of high-level radioactive waste and glass raw materials.

【0007】さらにこの発明の第2の実施態様は、一対
の交流電極を内部に具備する溶融炉内に高レベル放射性
廃棄物とガラス原料とを投入し、該交流電極に交流電流
を通電することにより該交流電極間の高レベル放射性廃
棄物とガラス原料とを直接通電加熱して混合溶融した
後、該混合溶融物を溶融炉から取り出して冷却しガラス
固化体とすることからなる高レベル放射性廃棄物の固化
処理に際して、該溶融炉内の混合溶融物に一対の直流電
極を挿入し、該直流電極を介して直流電流を通電して電
気分解を行い、この電気分解により酸化または還元され
る混合溶融物中の元素を該直流電極表面または該混合溶
融物中に析出させることを特徴とする高レベル放射性廃
棄物とガラス原料との混合溶融物から元素を分離する方
法である。
In a second embodiment of the present invention, a high-level radioactive waste and a glass raw material are charged into a melting furnace having a pair of AC electrodes therein, and an AC current is applied to the AC electrodes. The high-level radioactive waste between the AC electrode and the glass material is directly heated by heating and mixed and melted, and then the mixed molten material is taken out of a melting furnace and cooled to form a vitrified high-level radioactive waste. During the solidification process, a pair of DC electrodes is inserted into the mixed melt in the melting furnace, and a DC current is passed through the DC electrodes to perform electrolysis. A method for separating an element from a mixed melt of a high-level radioactive waste and a glass raw material, wherein an element in the melt is deposited on the surface of the direct current electrode or the mixed melt.

【0008】上記したこの発明の方法によれば、同一の
ガラス溶融炉において元素分離と混合溶融を行なうた
め、別途独立した元素分離工程を必要とせず、プロセス
が簡単であり、標準的なガラス溶融炉に若干の設備を付
加するだけで済むため設備コストも低減できる。さら
に、従来の元素分離方法に必要であった抽出溶媒や溶融
塩を使用する必要がなく、ガラス溶融炉内の混合溶融物
から直接元素分離できるため、発生する二次廃棄物量も
少なくなる。
According to the method of the present invention described above, since element separation and mixed melting are performed in the same glass melting furnace, a separate element separation step is not required, the process is simple, and standard glass melting is performed. Since only a few facilities need to be added to the furnace, facility costs can be reduced. Further, since it is not necessary to use an extraction solvent or a molten salt, which is required for the conventional element separation method, and the element can be directly separated from the mixed melt in the glass melting furnace, the amount of secondary waste generated is reduced.

【0009】[0009]

【発明の実施の形態】この発明の第1の実施態様を、図
1に示す装置の概略図を参照して説明する。高レベル廃
棄物とガラス原料の所定量を一対の電極2を備えた溶融
炉1に投入し、電極2に交流電源3から交流電流を通電
して直接通電加熱することにより混合溶融する。直接通
電加熱中に混合溶融物の温度を熱電対4および温度表示
器5により測定し、所定の溶融温度に達した段階で、電
極2に流す電流を電源切り替え器6により直流電源7か
らの直流電流に切り替える。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of the present invention will be described with reference to the schematic diagram of the apparatus shown in FIG. A predetermined amount of the high-level waste and the glass raw material are put into a melting furnace 1 provided with a pair of electrodes 2, and an alternating current is applied to the electrodes 2 from an AC power supply 3, and the mixture is directly melted by heating. The temperature of the mixed melt is measured by the thermocouple 4 and the temperature indicator 5 during direct current heating, and when a predetermined melting temperature is reached, the current flowing through the electrode 2 is changed by the power switch 6 from the DC power supply 7 Switch to current.

【0010】高温で溶融している混合溶融物中において
は、廃棄物成分の一部の元素はイオン化しており、電極
2を介して通電した直流電流の電位が、イオン化された
元素が有する電解電位と同じであれば、イオン化された
元素は還元あるいは酸化されて、電極2表面あるいは混
合溶融物中に析出分離する。
[0010] In the mixed melt that is melted at a high temperature, some elements of the waste components are ionized, and the potential of the direct current passed through the electrode 2 changes the potential of the ionized element. If the potential is the same, the ionized element is reduced or oxidized and precipitates and separates on the surface of the electrode 2 or in the mixed melt.

【0011】廃棄物成分の一部の元素が分離された後の
混合溶融物は、標準的なガラス固化プロセスと同じよう
に、溶融炉1底部のノズル8から流下させて取り出し、
キャニスター等の貯蔵容器(図示せず)に流し込んでガ
ラス固化体とする。
The mixed melt after some of the elements of the waste components have been separated is removed by flowing down from the nozzle 8 at the bottom of the melting furnace 1 in the same manner as in a standard vitrification process.
It is poured into a storage container (not shown) such as a canister to be a vitrified body.

【0012】図2は、この発明の第2の実施態様を実施
するための装置概略図であり、図1と同じ部材は同じ参
照番号を付すことにより説明を省略する。第2の実施態
様は、専ら交流電流を流すための交流電極11を具備し
た既存の溶融炉1を使用してこの発明の元素分離方法を
行なうものである。交流電極11を介して交流電源7か
らの交流電流により直接通電加熱を行い、混合溶融物が
所定の溶融温度に達した段階で交流電源7を切る。次い
で、溶融炉内の混合溶融物中に一対の直流電極12を挿
入し、直流電源7より直流電流を通電することにより、
上述したと同様の原理で、イオン化された元素が還元あ
るいは酸化されて、直流電極12表面あるいは混合溶融
物中に析出分離する。
FIG. 2 is a schematic view of an apparatus for carrying out a second embodiment of the present invention. The same members as those in FIG. 1 are denoted by the same reference numerals, and description thereof will be omitted. In the second embodiment, the element separation method of the present invention is performed using an existing melting furnace 1 provided with an AC electrode 11 for exclusively supplying an AC current. Direct heating is performed by an AC current from the AC power supply 7 via the AC electrode 11, and the AC power supply 7 is turned off when the mixed melt reaches a predetermined melting temperature. Next, by inserting a pair of DC electrodes 12 into the mixed melt in the melting furnace and applying a DC current from the DC power supply 7,
According to the same principle as described above, the ionized element is reduced or oxidized and precipitates and separates on the surface of the DC electrode 12 or in the mixed melt.

【0013】[0013]

【実施例】高レベル廃棄物とガラス原料とを、溶融炉内
で直接通電加熱により混合溶融したものを模擬する廃棄
物ガラスを調製した。この模擬廃棄物ガラスの組成は表
1の通りである。
EXAMPLE A waste glass simulating a high-level waste and a glass material mixed and melted in a melting furnace by direct current heating was prepared. Table 1 shows the composition of this simulated waste glass.

【0014】 [0014]

【0015】この模擬廃棄物ガラスをセラミックス製る
つぼに入れて電気炉内に置きヒータで間接加熱して、る
つぼ内の模擬廃棄物ガラスを1200℃に溶融した。次
いで、電気炉上部に設けた開放部からインコネル製の一
対の電極をるつぼ内の溶融物に挿入し、3.25Aの直
流電流を23分間通電して定電流電解を行なった。通電
終了後、るつぼから電極を取り出し、陰極表面の析出物
をX線マイクロアナライザー(EPMA)で分析した。
陰極表面の異なる部分〜を分析した結果をそれぞれ
図3〜図8に示す。これらの図からわかるように、陰極
表面に析出した主な元素は、白金族元素であるPd,R
u,Rhの他に、Moが認められた。
The simulated waste glass was placed in a ceramic crucible, placed in an electric furnace, and heated indirectly with a heater to melt the simulated waste glass in the crucible to 1200 ° C. Next, a pair of electrodes made of Inconel was inserted into the melt in the crucible from an opening provided in the upper part of the electric furnace, and a DC current of 3.25 A was supplied for 23 minutes to perform constant current electrolysis. After the completion of the energization, the electrode was taken out of the crucible, and the deposit on the cathode surface was analyzed with an X-ray microanalyzer (EPMA).
The results of analyzing different parts of the cathode surface are shown in FIGS. As can be seen from these figures, the main elements deposited on the cathode surface are the platinum group elements Pd, R
In addition to u and Rh, Mo was observed.

【0016】なお、供試した模擬廃棄物ガラスの重量8
1gに対して、定電流電解後の陰極表面の析出物重量は
約1gであり、そのうち白金族元素は約0.3gであっ
た。すなわち、廃棄物成分のうち析出物として分離回収
された元素の回収率は1.2%であり、そのうちの白金
族元素の回収率は37%となった。
The weight of the simulated waste glass tested was 8
With respect to 1 g, the weight of the precipitate on the cathode surface after the constant current electrolysis was about 1 g, of which the platinum group element was about 0.3 g. That is, the recovery rate of elements separated and recovered as precipitates among the waste components was 1.2%, of which the recovery rate of platinum group elements was 37%.

【0017】[0017]

【発明の効果】以上説明したところからわかるようにこ
の発明によれば、高レベル廃棄物とガラス原料とを溶融
炉内で混合溶融するガラス固化プロセスにおいて、溶融
炉内の混合溶融物に直流電流を流すことにより、廃棄物
成分から白金族元素等の有用な元素を分離することがで
きる。
As can be seen from the above description, according to the present invention, in the vitrification process of mixing and melting high-level waste and glass raw materials in a melting furnace, a direct current is applied to the mixed melt in the melting furnace. , It is possible to separate useful elements such as platinum group elements from waste components.

【0018】すなわちこの発明の方法を採用することに
より、高レベル廃棄物から元素を分離するための前処理
を必要とせず、従って二次廃棄物発生量が少なく、しか
も簡単かつ有効に廃棄物成分から元素を分離することが
できるガラス固化プロセスが提供できるものである。
That is, by employing the method of the present invention, a pretreatment for separating elements from high-level waste is not required, so that the amount of secondary waste generated is small, and the waste component can be simply and effectively used. Can provide a vitrification process that can separate elements from the glass.

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

【図1】この発明の第1の実施態様に好ましく使用でき
る装置の概念図。
FIG. 1 is a conceptual diagram of an apparatus that can be preferably used in the first embodiment of the present invention.

【図2】この発明の第2の実施態様に好ましく使用でき
る装置の概念図。
FIG. 2 is a conceptual diagram of an apparatus that can be preferably used in a second embodiment of the present invention.

【図3】実施例における陰極部分の析出物のEPMA
分析結果のグラフ。
FIG. 3 shows EPMA of a deposit at a cathode portion in Examples.
Analysis result graph.

【図4】実施例における陰極部分の析出物のEPMA
分析結果のグラフ。
FIG. 4 shows EPMA of a deposit at a cathode portion in Examples.
Analysis result graph.

【図5】実施例における陰極部分の析出物のEPMA
分析結果のグラフ。
FIG. 5 shows EPMA of a deposit at a cathode portion in Examples.
Analysis result graph.

【図6】実施例における陰極部分の析出物のEPMA
分析結果のグラフ。
FIG. 6 shows EPMA of a deposit at a cathode portion in Examples.
Analysis result graph.

【図7】実施例における陰極部分の析出物のEPMA
分析結果のグラフ。
FIG. 7 shows EPMA of a deposit at a cathode portion in an example.
Analysis result graph.

【図8】実施例における陰極部分の析出物のEPMA
分析結果のグラフ。
FIG. 8 shows EPMA of a deposit at a cathode portion in Examples.
Analysis result graph.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 河村 和廣 茨城県那珂郡東海村大字村松4番地33 動力炉・核燃料開発事業団東海事業所内 (58)調査した分野(Int.Cl.6,DB名) G21F 9/16 G21F 9/06 G21F 9/30 ────────────────────────────────────────────────── ─── front page of the continuation (72) inventor Kawamura Kazuhiro Ibaraki Prefecture Naka-gun, Tokai-mura, Oaza Muramatsu address 4 33 power reactor and nuclear fuel development Corporation Tokai plant (58) investigated the field (Int.Cl. 6, DB G21F 9/16 G21F 9/06 G21F 9/30

Claims (2)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】 一対の電極を内部に具備する溶融炉内に
高レベル放射性廃棄物とガラス原料とを投入し、該電極
に交流電流を通電することにより該電極間の高レベル放
射性廃棄物とガラス原料とを直接通電加熱して混合溶融
した後、該混合溶融物を溶融炉から取り出して冷却しガ
ラス固化体とすることからなる高レベル放射性廃棄物の
固化処理に際して、該溶融炉内の混合溶融物に該電極を
介して直流電流を通電して電気分解を行い、この電気分
解により酸化または還元される混合溶融物中の元素を該
電極表面または該混合溶融物中に析出させることを特徴
とする高レベル放射性廃棄物とガラス原料との混合溶融
物から元素を分離する方法。
1. A high-level radioactive waste and a glass raw material are charged into a melting furnace having a pair of electrodes therein, and an alternating current is applied to the electrodes to reduce the high-level radioactive waste between the electrodes. After directly heating and mixing and melting the glass raw material, the mixed melt is taken out of the melting furnace and cooled to form a vitrified body. A direct current is applied to the melt through the electrode to perform electrolysis, and the elements in the mixed melt that are oxidized or reduced by the electrolysis are deposited on the electrode surface or the mixed melt. A method for separating elements from a mixed melt of a high-level radioactive waste and a glass raw material.
【請求項2】 一対の交流電極を内部に具備する溶融炉
内に高レベル放射性廃棄物とガラス原料とを投入し、該
交流電極に交流電流を通電することにより該交流電極間
の高レベル放射性廃棄物とガラス原料とを直接通電加熱
して混合溶融した後、該混合溶融物を溶融炉から取り出
して冷却しガラス固化体とすることからなる高レベル放
射性廃棄物の固化処理に際して、該溶融炉内の混合溶融
物に一対の直流電極を挿入し、該直流電極を介して直流
電流を通電して電気分解を行い、この電気分解により酸
化または還元される混合溶融物中の元素を該直流電極表
面または該混合溶融物中に析出させることを特徴とする
高レベル放射性廃棄物とガラス原料との混合溶融物から
元素を分離する方法。
2. A high-level radioactive waste and a glass raw material are charged into a melting furnace having a pair of alternating current electrodes therein, and an alternating current is applied to the alternating current electrodes. In the solidification treatment of high-level radioactive waste, the waste and the glass raw material are directly heated by heating and mixed and melted, and then the mixed melt is taken out of the melting furnace and cooled to form a vitrified material. A pair of DC electrodes is inserted into the mixed melt in the inside, and a DC current is passed through the DC electrode to perform electrolysis, and the elements in the mixed melt that are oxidized or reduced by the electrolysis are removed by the DC electrode. A method for separating an element from a mixed melt of a high-level radioactive waste and a glass raw material, wherein the element is deposited on a surface or in the mixed melt.
JP19731696A 1996-07-26 1996-07-26 Elemental separation method from mixed melt of high-level radioactive waste and glass raw material Expired - Fee Related JP2966349B2 (en)

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Application Number Priority Date Filing Date Title
JP19731696A JP2966349B2 (en) 1996-07-26 1996-07-26 Elemental separation method from mixed melt of high-level radioactive waste and glass raw material

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JPH1039094A JPH1039094A (en) 1998-02-13
JP2966349B2 true JP2966349B2 (en) 1999-10-25

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Publication number Priority date Publication date Assignee Title
EP2178093B1 (en) * 2008-10-16 2010-11-24 Orion Tech Anstalt Treatment of liquid wastes containing heavy metals

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