JPS6356520B2 - - Google Patents
Info
- Publication number
- JPS6356520B2 JPS6356520B2 JP30271286A JP30271286A JPS6356520B2 JP S6356520 B2 JPS6356520 B2 JP S6356520B2 JP 30271286 A JP30271286 A JP 30271286A JP 30271286 A JP30271286 A JP 30271286A JP S6356520 B2 JPS6356520 B2 JP S6356520B2
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- resin composition
- monomer
- dry powder
- mixture
- 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
Links
- 239000002901 radioactive waste Substances 0.000 claims description 15
- 239000000203 mixture Substances 0.000 claims description 13
- 239000000843 powder Substances 0.000 claims description 13
- 239000011342 resin composition Substances 0.000 claims description 11
- 229920005989 resin Polymers 0.000 claims description 9
- 239000011347 resin Substances 0.000 claims description 9
- 239000000178 monomer Substances 0.000 claims description 8
- 229920001187 thermosetting polymer Polymers 0.000 claims description 8
- 239000010857 liquid radioactive waste Substances 0.000 claims description 7
- 239000002480 mineral oil Substances 0.000 claims description 5
- 235000010446 mineral oil Nutrition 0.000 claims description 5
- 239000007787 solid Substances 0.000 claims description 5
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 claims description 5
- 239000003960 organic solvent Substances 0.000 claims description 3
- 150000001338 aliphatic hydrocarbons Chemical class 0.000 claims description 2
- 150000004945 aromatic hydrocarbons Chemical class 0.000 claims description 2
- 230000007774 longterm Effects 0.000 claims description 2
- 238000004519 manufacturing process Methods 0.000 claims description 2
- SWZDQOUHBYYPJD-UHFFFAOYSA-N tridodecylamine Chemical compound CCCCCCCCCCCCN(CCCCCCCCCCCC)CCCCCCCCCCCC SWZDQOUHBYYPJD-UHFFFAOYSA-N 0.000 claims description 2
- 238000000034 method Methods 0.000 description 7
- CYTYCFOTNPOANT-UHFFFAOYSA-N Perchloroethylene Chemical group ClC(Cl)=C(Cl)Cl CYTYCFOTNPOANT-UHFFFAOYSA-N 0.000 description 5
- PPBRXRYQALVLMV-UHFFFAOYSA-N Styrene Natural products C=CC1=CC=CC=C1 PPBRXRYQALVLMV-UHFFFAOYSA-N 0.000 description 5
- 229950011008 tetrachloroethylene Drugs 0.000 description 5
- LYCAIKOWRPUZTN-UHFFFAOYSA-N Ethylene glycol Chemical compound OCCO LYCAIKOWRPUZTN-UHFFFAOYSA-N 0.000 description 4
- SNRUBQQJIBEYMU-UHFFFAOYSA-N dodecane Chemical compound CCCCCCCCCCCC SNRUBQQJIBEYMU-UHFFFAOYSA-N 0.000 description 4
- DNIAPMSPPWPWGF-UHFFFAOYSA-N Propylene glycol Chemical compound CC(O)CO DNIAPMSPPWPWGF-UHFFFAOYSA-N 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- 239000002699 waste material Substances 0.000 description 3
- RPNUMPOLZDHAAY-UHFFFAOYSA-N Diethylenetriamine Chemical compound NCCNCCN RPNUMPOLZDHAAY-UHFFFAOYSA-N 0.000 description 2
- 235000008504 concentrate Nutrition 0.000 description 2
- 239000012141 concentrate Substances 0.000 description 2
- 239000003822 epoxy resin Substances 0.000 description 2
- WGCNASOHLSPBMP-UHFFFAOYSA-N hydroxyacetaldehyde Natural products OCC=O WGCNASOHLSPBMP-UHFFFAOYSA-N 0.000 description 2
- 229920000647 polyepoxide Polymers 0.000 description 2
- 230000001988 toxicity Effects 0.000 description 2
- 231100000419 toxicity Toxicity 0.000 description 2
- VEXZGXHMUGYJMC-UHFFFAOYSA-M Chloride anion Chemical compound [Cl-] VEXZGXHMUGYJMC-UHFFFAOYSA-M 0.000 description 1
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 description 1
- VGGSQFUCUMXWEO-UHFFFAOYSA-N Ethene Chemical compound C=C VGGSQFUCUMXWEO-UHFFFAOYSA-N 0.000 description 1
- 239000005977 Ethylene Substances 0.000 description 1
- KJTLSVCANCCWHF-UHFFFAOYSA-N Ruthenium Chemical compound [Ru] KJTLSVCANCCWHF-UHFFFAOYSA-N 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 235000014666 liquid concentrate Nutrition 0.000 description 1
- 229920000768 polyamine Polymers 0.000 description 1
- 238000006116 polymerization reaction Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 229910052707 ruthenium Inorganic materials 0.000 description 1
- 238000003756 stirring Methods 0.000 description 1
- 125000003011 styrenyl group Chemical group [H]\C(*)=C(/[H])C1=C([H])C([H])=C([H])C([H])=C1[H] 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 229920006305 unsaturated polyester Polymers 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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
- G21F9/301—Processing by fixation in stable solid media
- G21F9/307—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Compositions Of Macromolecular Compounds (AREA)
- Fertilizers (AREA)
- Water Treatment By Sorption (AREA)
- Separation, Recovery Or Treatment Of Waste Materials Containing Plastics (AREA)
Description
本発明は樹脂と単量体との共重合可能な熱硬化
性樹脂組成物に有機液体放射性廃棄物をまず添加
混合し、さらにこの混合物に乾燥粉末放射性廃棄
物を均一に混合した後、樹脂と単量体とを環境温
度で共重合させ、固体ブロツクを作製する放射性
廃棄物の処理方法に係るものである。
特公昭56−33680号には乾燥粉末状の放射性廃
棄物を環境温度で樹脂と単量体との共重合可能な
熱硬化性樹脂組成物に配合し、そして前記の樹脂
と単量体とを共重合させて固体ブロツクを得るよ
うにした放射性廃棄物を処理する方法が記載され
ている。例えば、液体濃縮物、粉末化廃棄物及び
燃料廃棄物の灰化により生成した灰などの放射性
廃棄物はあらかじめ乾燥粉末状態にされたもので
あれば、上記方法により処理することができる。
共重合可能な熱硬化性樹脂組成物における樹脂は
好ましくは不飽和ポリエステル、例えばグリコー
ルマレオフタレートであり、かつ単量体は好まし
くはスチレンである。
本発明は、まず放射性有機液体を前記樹脂組成
物中に均一に混合した後、乾燥粉末廃棄物を混合
させると、その粉末廃棄物のみを樹脂組成物に混
合させた場合よりも多くの量の乾燥粉末を混合含
有させ得ることを見出し、ここに完成された。本
発明は、鉱油、トリブチルフオスフエートのよう
な原子力発電所、再処理工場などから発生する有
機液体放射性廃棄物を乾燥粉末放射性廃棄物と同
時に処理し、長期貯蔵または最終処分に適する固
体ブロツクを製造する方法を提供するものであ
る。
本発明において、重合前に樹脂組成物に添加さ
れる有機液体放射性廃棄物の量は該組成物の10な
いし30重量％が好適である。
有機液体放射性廃棄物としては脂肪族炭化水
素、芳香族炭化水素、塩素化有機溶媒、鉱油、ト
リブチルフオスフエートまたはトリラウリルアミ
ンから選択される１種又は２種以上の有機液体が
最も一般的である。
本発明に適用される樹脂と単量体との混合物か
らなる熱硬化性樹脂組成物の例としては特公昭56
−33680号に記載されたグリコールマレオフタレ
ートとスチレンとの混合物あるいはエポキシ樹脂
とジエチレントリアミンのようなポリアミンの混
合物である。
以下、実施例によつて本発明をさらに詳細に説
明するが、これらの例は本発明の理解を容易にす
るためのものであつて、本発明を限定するもので
はない。
実施例
75重量％のプロピレングリコールマレオフタレ
ート及び９〜12重量％のスチレンを含有する共重
合可能な熱硬化性樹脂組成物100ｇに10-4μキユリ
ー／mlのコバルト60を含有する20ｇの過クロルエ
チレンを添加した。次に下に記載した方法により
得られる乾燥粉末放射性廃棄物混合物の120ｇと
配合することが可能であつた。過クロルエチレン
の不存在のほかは同一の条件下では樹脂に乾燥粉
末放射性廃棄物100ｇのみを配合することが可能
であつた。
上記乾燥粉末放射性廃棄物混合物は下記のとお
りにして得られる：
前記粉末を得るための液状流出物の中程度の放射
能をおびている濃縮物は以下の二つの表に示され
る組成ならびに放射能を有する。
The present invention involves first adding and mixing organic liquid radioactive waste to a thermosetting resin composition capable of copolymerizing resin and monomer, and then uniformly mixing dry powder radioactive waste into this mixture. This method involves copolymerizing radioactive waste with monomers at ambient temperature to produce a solid block. In Japanese Patent Publication No. 56-33680, radioactive waste in the form of dry powder is blended into a thermosetting resin composition capable of copolymerizing a resin and a monomer at ambient temperature, and then the resin and monomer are combined. A method is described for treating radioactive waste by copolymerizing it to obtain a solid block. For example, radioactive wastes such as liquid concentrates, pulverized wastes, and ash produced by incineration of fuel wastes can be treated by the method described above, provided they have been previously reduced to a dry powder state.
The resin in the copolymerizable thermosetting resin composition is preferably an unsaturated polyester, such as glycol maleophthalate, and the monomer is preferably styrene. The present invention provides that if the radioactive organic liquid is first uniformly mixed into the resin composition and then the dry powder waste is mixed therein, a larger amount of It was discovered and completed that it is possible to mix and contain dry powders. The present invention treats organic liquid radioactive wastes generated from nuclear power plants, reprocessing plants, etc., such as mineral oil and tributyl phosphate, simultaneously with dry powder radioactive wastes to form solid blocks suitable for long-term storage or final disposal. The present invention provides a method for manufacturing. In the present invention, the amount of organic liquid radioactive waste added to the resin composition before polymerization is preferably 10 to 30% by weight of the composition. The most common organic liquid radioactive waste is one or more organic liquids selected from aliphatic hydrocarbons, aromatic hydrocarbons, chlorinated organic solvents, mineral oil, tributyl phosphate, or trilaurylamine. be. As an example of a thermosetting resin composition comprising a mixture of a resin and a monomer that can be applied to the present invention,
-33680, a mixture of glycol maleophthalate and styrene, or a mixture of an epoxy resin and a polyamine such as diethylenetriamine. EXAMPLES Hereinafter, the present invention will be explained in more detail with reference to Examples, but these examples are intended to facilitate understanding of the present invention, and are not intended to limit the present invention. Example 100 g of a copolymerizable thermosetting resin composition containing 75% by weight of propylene glycol maleophthalate and 9 to 12% by weight of styrene to 20 g of perchloride containing 10 −4 μKyries/ml of cobalt-60. Added ethylene. It was then possible to combine with 120 g of a dry powdered radioactive waste mixture obtained by the method described below. Under identical conditions except for the absence of perchlorethylene, it was possible to incorporate only 100 g of dry powder radioactive waste into the resin. The dry powder radioactive waste mixture is obtained as follows: The moderately radioactive concentrate of the liquid effluent to obtain the powder has the composition and radioactivity shown in the following two tables. have
【表】【table】
【表】
照
これらの濃縮物を薄層蒸発器中で乾燥した。得
られた乾燥粉末は0.3％以下の水含有率を有する。
実施例
過クロルエチレンの代りにルテニウム（10-3キ
ユリー／m3）で汚染された、TBP（30％）とドデ
カン（70％）の混合物を用いたこと以外実施例
と同一の条件下で、実質上同一の結果が得られ
た。
実施例
実施例のTBPとドデカンの混合物の代りに
鉱油を用いたこと以外は実施例と同一の条件下
で、実質上同一の結果が得られた。
実施例
エポキシ樹脂100重量部とジエチレントリアミ
ン66重量部とからなる共重合可能な熱硬化性樹脂
組成物の100ｇに過クロルエチレン20ｇを添加し
た。次に実施例において示したのと同様の乾燥
粉末放射性廃棄物の混合物120ｇを撹拌しながら
前記の樹脂組成物の混和させて硬化した。24時間
後に固化体ブロツクが得られた。
過クロルエチレンを加えないで、同一の条件下
で行つた場合、乾燥粉末放射性廃棄物100ｇ以上
の配合は不可能であつた。
実施例
実施例と同一条件で過クロルエチレンの代り
に鉱油を用いた場合も、実施例と実質上同一の
結果が得られた。
以上のように本発明方法は、一定量の樹脂によ
つて特公昭56−33680号の方法におけるより更に
多くの乾燥粉末放射性廃棄物が処分できるばかり
でなく、また極めて高い放射性を有するかまたは
腐食性又は毒性である化学的性質の理由により灰
化の困難な有機溶媒からなる有機液体放射性廃棄
物をも一緒に処理できることにある。[Table] These concentrates were dried in a thin layer evaporator. The dry powder obtained has a water content of less than 0.3%. Example Under the same conditions as in the example except that a mixture of TBP (30%) and dodecane (70%) contaminated with ruthenium (10 −3 curies/m 3 ) was used instead of perchlorethylene. Virtually identical results were obtained. Example Substantially the same results were obtained under the same conditions as in the example except that mineral oil was used instead of the mixture of TBP and dodecane in the example. Example 20 g of perchlorethylene was added to 100 g of a copolymerizable thermosetting resin composition consisting of 100 parts by weight of epoxy resin and 66 parts by weight of diethylenetriamine. Next, 120 g of a mixture of dry powdered radioactive waste similar to that shown in Examples was mixed with the resin composition and cured with stirring. A solid block was obtained after 24 hours. When carried out under the same conditions without adding perchlorethylene, it was not possible to blend more than 100 g of dry powder radioactive waste. Example When mineral oil was used instead of perchlorethylene under the same conditions as in the example, substantially the same results as in the example were obtained. As described above, the method of the present invention not only can dispose of even more dry powder radioactive waste with a certain amount of resin than the method of Japanese Patent Publication No. 56-33680, but also can dispose of radioactive waste that is extremely highly radioactive or corrosive. The advantage is that organic liquid radioactive waste consisting of an organic solvent that is difficult to ash due to its chemical properties such as toxicity or toxicity can also be treated.
Claims (1)
する固体ブロツクの製造方法であつて、脂肪族炭
化水素、芳香族炭化水素、塩素化有機溶媒、鉱
油、トリブチルフオスフエートまたはトリラウリ
ルアミンから選択される１種または２種以上の有
機溶液からなる有機液体放射性廃棄物を樹脂と単
量体との共重合可能な熱硬化性樹脂組成物に加
え、該有機液体放射性廃棄物とこの組成物との混
合物を乾燥粉末放射性廃棄物と均一に撹拌混合
し、熱硬化性樹脂組成物中の樹脂と単量体とを環
境温度で共重合させることを特徴とする方法。1. A method for producing solid blocks suitable for long-term storage or final disposal of radioactive waste, selected from aliphatic hydrocarbons, aromatic hydrocarbons, chlorinated organic solvents, mineral oil, tributyl phosphate or trilaurylamine. An organic liquid radioactive waste consisting of one or more organic solutions is added to a thermosetting resin composition capable of copolymerizing a resin and a monomer, and a mixture of the organic liquid radioactive waste and this composition is added. is uniformly stirred and mixed with dry powder radioactive waste, and the resin and monomer in the thermosetting resin composition are copolymerized at ambient temperature.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7317974A FR2230041A2 (en) | 1971-03-16 | 1973-05-17 | Elimination of radioactive waste material |
| FR7317974 | 1973-05-17 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62167500A JPS62167500A (en) | 1987-07-23 |
| JPS6356520B2 true JPS6356520B2 (en) | 1988-11-08 |
Family
ID=9119504
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP49055335A Pending JPS5020200A (en) | 1973-05-17 | 1974-05-17 | |
| JP30271286A Granted JPS62167500A (en) | 1973-05-17 | 1986-12-18 | Method of processing radioactive waste |
Family Applications Before (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP49055335A Pending JPS5020200A (en) | 1973-05-17 | 1974-05-17 |
Country Status (6)
| Country | Link |
|---|---|
| JP (2) | JPS5020200A (en) |
| BE (1) | BE814594R (en) |
| DE (1) | DE2422240C2 (en) |
| ES (1) | ES426410A2 (en) |
| GB (1) | GB1418277A (en) |
| IT (1) | IT1048509B (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5481500A (en) * | 1977-12-09 | 1979-06-28 | Nippon Atom Ind Group Co Ltd | Solidifying treatment into plastic of radioactive waste |
| US4400313A (en) | 1980-06-30 | 1983-08-23 | The Dow Chemical Company | Process for waste encapsulation |
| DE4324818C2 (en) * | 1993-07-23 | 2002-06-27 | Framatome Anp Gmbh | Process for the disposal of ion exchange resin |
| CN109727697B (en) * | 2017-10-31 | 2024-04-09 | 中核核电运行管理有限公司 | High-radioactivity waste receiving device |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3463738A (en) * | 1968-05-01 | 1969-08-26 | Atomic Energy Commission | Conversion and containment of radioactive organic liquids into solid form |
| FR2129836B1 (en) * | 1971-03-16 | 1974-04-26 | Commissariat Energie Atomique |
-
1974
- 1974-05-06 BE BE143960A patent/BE814594R/en active
- 1974-05-08 IT IT6844374A patent/IT1048509B/en active
- 1974-05-08 DE DE19742422240 patent/DE2422240C2/en not_active Expired
- 1974-05-09 GB GB2060874A patent/GB1418277A/en not_active Expired
- 1974-05-17 JP JP49055335A patent/JPS5020200A/ja active Pending
- 1974-05-17 ES ES426410A patent/ES426410A2/en not_active Expired
-
1986
- 1986-12-18 JP JP30271286A patent/JPS62167500A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| IT1048509B (en) | 1980-12-20 |
| BE814594R (en) | 1974-09-02 |
| DE2422240C2 (en) | 1982-11-18 |
| ES426410A2 (en) | 1977-10-16 |
| DE2422240A1 (en) | 1974-12-05 |
| JPS62167500A (en) | 1987-07-23 |
| JPS5020200A (en) | 1975-03-03 |
| GB1418277A (en) | 1975-12-17 |
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