JPS5918497A - Method of cleaning off-gas producing at vitrification of radioactive waste - Google Patents
Method of cleaning off-gas producing at vitrification of radioactive wasteInfo
- Publication number
- JPS5918497A JPS5918497A JP58112979A JP11297983A JPS5918497A JP S5918497 A JPS5918497 A JP S5918497A JP 58112979 A JP58112979 A JP 58112979A JP 11297983 A JP11297983 A JP 11297983A JP S5918497 A JPS5918497 A JP S5918497A
- Authority
- JP
- Japan
- Prior art keywords
- vitrification
- glass
- radioactive waste
- filter
- cleaning
- 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
- G21F9/02—Treating gases
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Filtering Materials (AREA)
- Processing Of Solid Wastes (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】
本発明は放射性廃棄物のガラス化の際に生じる排気のフ
ィルターによる浄化法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for purifying exhaust gas produced during the vitrification of radioactive waste using a filter.
燃焼ずみ焼料要素の再処理からの高放射性の廃棄物およ
び廃液を埋込む方法としてガラス化が実施された。この
ためには、廃棄物または排液はガラス、有利にはホウケ
イ酸塩ガラスからの融液に加えられ、生じた混合物は凝
固後最終貯蔵所に供給される。Vitrification has been implemented as a method of embedding highly radioactive waste and effluents from the reprocessing of burnt pyrotechnic elements. For this purpose, the waste or effluent is added to the melt from a glass, preferably a borosilicate glass, and the resulting mixture is fed after solidification to a final storage.
廃棄物の高い放射性のために、ガス状またはダスト状の
放射性物質を含有するこれらガラス化装置からの排気は
、注意深く浄化しなければならない。その際、最小粒度
のダスト状物質が特別な問題を生じる。これを除去する
ためには、主に２つの方法およびその組み合せが使用さ
れる。種々の構造の洗浄器は５μｍより大きい直径を有
する粒子を分離出来るが、これよりも小さい粒子に対し
ては捕捉度が充分ではない。この場合、洗浄水はしかし
付加的な工程で処理しなければならない。織布フィルタ
ーまたはフリースフィルターならびに繊維充填物は最小
の粒子をも捕捉するが、ダスト濃度の増加につれて交換
しかつそれらの高い放射性含量のために安。Due to the high radioactivity of the waste, the exhaust air from these vitrification devices containing radioactive materials in gaseous or dusty form must be carefully purified. In this case, dust-like substances of the smallest particle size pose special problems. To remove this, two main methods and combinations thereof are used. Cleaners of various constructions are capable of separating particles with diameters greater than 5 μm, but the retention of smaller particles is not sufficient. In this case, however, the wash water must be treated in an additional step. Woven or fleece filters as well as fiber fillings trap even the smallest particles but are cheap to replace as dust concentrations increase and due to their high radioactive content.
全な最終貯蔵所に供給せねばならない。それにより二次
廃棄物が生じる。All final repositories must be supplied. This creates secondary waste.
従って、本発明の課題は、放射性廃棄物のガラス化の際
に生じる排気を、付加的な工程を必要としないかまたは
二次廃棄物の生じる事なしに、最小のダスト状含分をも
除去する事の出来るフィルターによって浄化する方法な
開発する事であった。It is therefore an object of the present invention to remove even the smallest dusty content of the exhaust gas produced during the vitrification of radioactive waste without the need for additional steps or without the generation of secondary waste. The goal was to develop a method of purification using a filter that could be used.
この課題は本発明によれば、フィルターとしてガラスか
ら成るかまたはガラス成分から成る微粒状材料から成る
堆積層を使用１〜、濾材を放射性有害物質の負荷後にガ
ラス化装置のガラス融液に添加することにより解決した
。According to the invention, this task is achieved by using as a filter a deposited layer of a finely divided material made of glass or of a glass component. It was resolved by this.
このようなフィルター、たとえば特に０１〜Ｑ、 ３
ｍｍの直径を有する粒子から成る高さ１０硼の層は、直
径０．３〜０５μｍの間のあらゆる粒子の９９９５％よ
り多くを分離する事が出来た。Such filters, for example especially 01-Q, 3
A layer 10 mm high of particles with a diameter of mm was able to separate more than 9995% of all particles between 0.3 and 05 μm in diameter.
ガラス融液の組成に影響を与・えないために、堆積層の
原料物質として有利には融液をつくるのに使用されるガ
ラス、特につまりホウケイ酸塩ガラスが使用される。ガ
ラスは粉砕し、篩別され、支持体上でフィルタとして使
用され、使用後融液に添加される。同様に、ガラス成分
、特にケイ砂から成る粒子も濾材として使用する事が出
来る。In order not to influence the composition of the glass melt, the starting material for the deposited layer is preferably the glass used to prepare the melt, in particular a borosilicate glass. The glass is crushed, sieved, used as a filter on a support and added to the melt after use. Particles consisting of glass components, especially silica sand, can likewise be used as filter media.
Claims (1)
ターによって浄化する方法において、フィルターとして
、ガラスまたはガラス成分から成る微粒状材料から成る
堆積層を使用し、濾材を放射性有害物質の負荷後、ガラ
ス化装置のガラス融液に添加する事を特徴とする、放射
性廃棄物のガラス化の際に生じる排気の浄化法。 ２ 濾材粒子が０１〜０．３ 、、の直径を有し、かつ
ホウケイ酸塩ガラスから成るかまたはケイ砂から成る、
特許請求の範囲第１項記載の方法・[Claims] 1. A method for purifying exhaust gas generated during the vitrification of radioactive waste using a filter, in which a deposited layer made of glass or a fine particulate material made of a glass component is used as the filter, and the filter material is radioactively harmful. A method for purifying the exhaust gas generated during the vitrification of radioactive waste, which is characterized by adding the substance to the glass melt in the vitrification equipment after loading it. 2. The filter media particles have a diameter of 0.01 to 0.3, and consist of borosilicate glass or of silica sand,
The method according to claim 1
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE32258984 | 1982-07-10 | ||
| DE3225898 | 1982-07-10 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5918497A true JPS5918497A (en) | 1984-01-30 |
Family
ID=6168155
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58112979A Pending JPS5918497A (en) | 1982-07-10 | 1983-06-24 | Method of cleaning off-gas producing at vitrification of radioactive waste |
Country Status (3)
| Country | Link |
|---|---|
| EP (1) | EP0102468B1 (en) |
| JP (1) | JPS5918497A (en) |
| DE (1) | DE3367818D1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62123399A (en) * | 1985-11-22 | 1987-06-04 | 日本碍子株式会社 | Method and device for melting and solidifying radioactive waste liquor |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62222198A (en) * | 1986-03-25 | 1987-09-30 | 動力炉・核燃料開発事業団 | Manufacture of cartridge for processing radioactive waste liquor |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3116131A (en) * | 1960-08-01 | 1963-12-31 | Victor Comptometer Corp | Method and materials for disposing of radioactive waste |
| GB949117A (en) * | 1961-12-20 | 1964-02-12 | Atomic Energy Authority Uk | Improvements in or relating to nuclear reactors |
| DE2731327C3 (en) * | 1977-07-12 | 1981-01-22 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Process for filtering dust from radioactive waste gases and equipment for carrying out the process |
| FR2476370A1 (en) * | 1980-02-20 | 1981-08-21 | Gagneraud Pere Et Fils Entr | Entrapping radioactive waste gases - by bubbling gas into silicate melt and rapidly solidifying |
-
1983
- 1983-06-24 JP JP58112979A patent/JPS5918497A/en active Pending
- 1983-06-28 EP EP83106274A patent/EP0102468B1/en not_active Expired
- 1983-06-28 DE DE8383106274T patent/DE3367818D1/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62123399A (en) * | 1985-11-22 | 1987-06-04 | 日本碍子株式会社 | Method and device for melting and solidifying radioactive waste liquor |
Also Published As
| Publication number | Publication date |
|---|---|
| EP0102468B1 (en) | 1986-11-20 |
| EP0102468A1 (en) | 1984-03-14 |
| DE3367818D1 (en) | 1987-01-08 |
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