JPH0677073B2 - Solidification material for radioactive waste treatment - Google Patents
Solidification material for radioactive waste treatmentInfo
- Publication number
- JPH0677073B2 JPH0677073B2 JP60269515A JP26951585A JPH0677073B2 JP H0677073 B2 JPH0677073 B2 JP H0677073B2 JP 60269515 A JP60269515 A JP 60269515A JP 26951585 A JP26951585 A JP 26951585A JP H0677073 B2 JPH0677073 B2 JP H0677073B2
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- waste treatment
- solidifying material
- radioactive
- solidified
- 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
Links
Landscapes
- Processing Of Solid Wastes (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Hard Magnetic Materials (AREA)
Description
【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、放射性廃棄物処理用固化材に関するものであ
る。TECHNICAL FIELD The present invention relates to a solidifying material for treating radioactive waste.
従来、例えばドラム缶又はその他の放射性廃棄物処理容
器内に放射性廃棄物を充填固化する為に、アスファル
ト、セメント等の固化材が用いられている。Conventionally, solidifying materials such as asphalt and cement have been used to fill and solidify radioactive waste in, for example, drums or other radioactive waste treatment containers.
そして、このような固化材によって固化された放射性廃
棄物処理固化体は、内部に充填されている放射性廃棄物
が外部に滲出しないように、出来るだけ緻密な組織を構
成していることが望ましいと言われている。Then, it is desirable that the radioactive waste treatment solidified by the solidifying material has a structure as dense as possible so that the radioactive waste filled inside does not exude to the outside. It is said.
しかし、放射性廃棄物処理固化体が緻密な組織を構成し
たものであると、それだけ充填密度が高く、無機質固化
体では重量の大きなものとなり、運搬その他の処理に際
して極めて面倒な欠点がある。However, if the radioactive waste treatment solidified body has a dense structure, the packing density is high, and the inorganic solidified body becomes heavy, which is a very troublesome drawback in transportation and other treatments.
又、これまでのセメント系固化材は、放射性廃棄物処理
容器内に上部注入によって充填する場合、流動性がそれ
程良くない為、均一に充填されにくく、均一に微細な末
端まで固化材を充填して固化させることが不充分である
といった欠点もある。In addition, the conventional cement-based solidifying material is difficult to fill uniformly when it is filled by top injection into a radioactive waste treatment container, so it is difficult to fill it uniformly, and the solidifying material is evenly filled to the fine ends. There is also a drawback that it is insufficient to solidify it.
本発明者は、固化材によって固化された放射性廃棄物処
理固化体に対する詳細な研究を行なった結果、この固化
体が均一に固化していれば緻密な組織を有するように構
成されている必要は必ずしも絶対条件なものではないこ
とを見い出し、例えば発泡構造のようなものでも差し支
えないことに気付き、固化性材料と起泡性材料とを含む
放射性廃棄物処理用固化材を発明するに至ったのであ
る。The present inventor has carried out a detailed study on the radioactive waste treatment solidified by the solidifying material, and as a result, if the solid is uniformly solidified, it is not necessary that the solid has a dense structure. They found that it was not absolutely necessary, and realized that a foamed structure could be used, for example, and invented a solidifying material for radioactive waste treatment containing a solidifying material and a foaming material. is there.
すなわち、本発明になる放射性廃棄物処理用固化材によ
る固化体は、内部に気泡を有する構造のものである為、
それだけ軽量なものであり、従ってハンドリング操作が
容易であるといった大きな特長をもたらすものであり、
又、この固化材は流動性が良い為、放射性廃棄物処理容
器内に均一充填させることが出来、従って得られる固化
体は固化材のバラツキが少なく、場所によって強度が足
らないといった欠点が起きることなく、例えば陸地処分
に要求されている一軸圧縮強度が30kg/cm2以上の要件を
も満たすことが出来るものであり、さらには内部に気泡
を有する構造である為、この固化体は凍結融解にも強い
といった特長を有している。That is, since the solidified body by the solidifying material for radioactive waste treatment according to the present invention has a structure having bubbles inside,
It is so lightweight that it brings great features such as easy handling.
In addition, since this solidifying material has good fluidity, it can be uniformly filled in the radioactive waste treatment container, and thus the solidified material obtained has the disadvantages that there is little variation in the solidifying material and the strength is insufficient depending on the location. However, for example, the uniaxial compressive strength required for land disposal can meet the requirement of 30 kg / cm 2 or more, and since it has a structure with bubbles inside, this solidified body is freeze-thawed. It also has the feature of being strong.
尚、この本発明になる放射性廃棄物処理用固化材による
固化体が独立気泡タイプのものである場合には、放射性
物質の滲出はより一層少なく、望ましいものである。In addition, when the solidified body by the solidifying material for treating radioactive waste according to the present invention is of the closed-cell type, leaching of radioactive material is further reduced, which is desirable.
又、この本発明になる放射性廃棄物処理用固化材に、固
化性材料及び起泡性材料のみではなく、例えばゼオライ
ト等の放射性物質の吸着材が含まれていると、放射性物
質の滲出をより完全に防止できることより望ましいもの
である。Further, when the solidifying material for treating radioactive waste according to the present invention contains not only the solidifying material and the foaming material but also the adsorbing material for radioactive substances such as zeolite, the exudation of the radioactive substances is further suppressed. It is more desirable that it can be completely prevented.
本発明は上記の知見を基にして達成されたものであり、
本発明は、固化性材料と起泡性材料と放射性物質吸着材
とを含むことを特徴とする放射性廃棄物処理用固化材を
提供するものである。The present invention has been achieved based on the above findings,
The present invention provides a solidifying material for treating radioactive waste, which comprises a solidifying material, a foaming material, and a radioactive substance adsorbing material.
尚、本発明における固化性材料としては、例えば一般的
にはセメントと水とがあり、又、起泡性材料としては、
例えば動物性加水分解蛋白質を主原料とした微細な独立
気泡を均一に生成せしむるマールＰ液（宝通商（株）
製）、モノクリート（第一化成産業（株）製）あるいは
界面活性剤タイプの中でも起泡性を呈するもの等があ
る。尚、言うまでもないが、界面活性剤と称されるもの
全てが起泡性を呈すると言うものではない。Incidentally, as the solidifying material in the present invention, for example, generally there are cement and water, and as the foaming material,
For example, Marl P liquid that uniformly produces fine closed cells mainly composed of animal hydrolyzed protein (Takara Tsusho Co., Ltd.)
Manufactured by Daiichi Kasei Sangyo Co., Ltd., and among surfactant types, there are those exhibiting foamability. Needless to say, not all of the so-called surfactants exhibit foaming properties.
そして、これら材料の配合割合は、処理される放射性廃
棄物の種類及び起泡性材料の起泡性能によっても多少の
差はあるが、例えばセメント：水：起泡性材料が重量比
で100:50〜70:1〜10の割合であることが望ましい。The mixing ratio of these materials is somewhat different depending on the type of radioactive waste to be treated and the foaming performance of the foaming material, but for example, cement: water: foaming material is 100: 100 by weight. A ratio of 50 to 70: 1 to 10 is desirable.
〔実施例１〕 ミキサーに水56重量部と普通ポルトランドセメント100
重量部とを混練してスラリー状のものとなし、これにマ
ールＰ液２重量部を入れて練り上げ、これを放射性廃棄
物が充填された容器内に充填し、固化させる。[Example 1] 56 parts by weight of water and 100 parts of ordinary Portland cement in a mixer
2 parts by weight of Marl P liquid is put into this and kneaded, and this is filled in a container filled with radioactive waste and solidified.
尚、上記水56重量部、普通ポルトランドセメント100重
量部及びマールＰ液２重量部からなる固化体の比重は1.
20であり、そしてこの固化体の材令28日の圧縮強度は95
kg/cm2であり、又、この固化体は内部に微細な独立気泡
を均一に有するものであり、放射性廃棄物処理用固化材
として好適なものである。The specific gravity of the solidified body composed of 56 parts by weight of water, 100 parts by weight of ordinary Portland cement and 2 parts by weight of Marl P liquid is 1.
20 and the 28-day compressive strength of this solidified body is 95.
It is kg / cm 2 , and this solidified body has fine closed cells uniformly inside, and is suitable as a solidifying material for treating radioactive waste.
〔実施例２〕 実施例１におけるマールＰ液を３重量部として同様に行
なう。[Example 2] The same procedure as in Example 1 was performed using 3 parts by weight of the Marl P liquid.
尚、この場合の水、普通ポルトランドセメント及びマー
ルＰ液からなる固化体の比重は1.00、材令28日の圧縮強
度は64kg/cm2のものであった。In this case, the specific gravity of the solidified body composed of water, ordinary Portland cement and Marl P liquid was 1.00 and the compressive strength on the 28th day was 64 kg / cm 2 .
〔実施例３〕 実施例１におけるマールＰ液を５重量部として同様に行
なう。[Example 3] The same procedure as in Example 1 was carried out using 5 parts by weight of Marl P liquid.
尚、この場合の水、普通ポルトランドセメント及びマー
ルＰ液からなる固化体の比重は0.80、材令28日の圧縮強
度は30kg/cm2のものであった。In this case, the specific gravity of the solidified body composed of water, ordinary Portland cement and Marl P liquid was 0.80, and the compressive strength on the 28th day was 30 kg / cm 2 .
尚、上記の実施例においては、比重および圧縮強度を調
べる目的のものであったことから、ゼオライト等の放射
性物質の吸着材を添加していなかったけれども、これら
を添加していても比重や圧縮強度には大差がない。In the above examples, since the purpose was to investigate the specific gravity and compressive strength, the adsorbent for radioactive substances such as zeolite was not added, but even if these are added, the specific gravity and compression There is not much difference in strength.
本発明に係る放射性廃棄物処理用固化材は、固化性材料
と起泡性材料と放射性物質吸着材とを含むものであるか
らこの固化材による固化体は内部に例えば独立した微細
な気泡を有する構造をしており、従ってそれだけ軽量な
ものであるから運搬等に際してのハンドリング操作が容
易であり、又、この固化材は流動性が良いので放射性廃
棄物処理容器内にスムーズで均一に充填させることがで
き、又、この固化材による固化体は内部に気泡を有して
いるので凍結融解にも強く、さらには陸地処分に要求さ
れている圧縮強度が30kg/cm2以上の条件をも満足させる
ことができ、しかも放射性物質の浸出は少なく、又、低
コストなものである等の特長を有する。Since the solidifying material for treating radioactive waste according to the present invention contains a solidifying material, a foaming material and a radioactive substance adsorbing material, the solidified material by this solidifying material has a structure having, for example, independent fine bubbles inside. Therefore, since it is so lightweight, it can be easily handled during transportation, etc. Also, since this solidifying material has good fluidity, it can be filled smoothly and uniformly in the radioactive waste treatment container. In addition, since the solidified material with this solidifying material has bubbles inside, it is also resistant to freeze-thawing, and further, it can satisfy the condition that the compressive strength required for land disposal is 30 kg / cm 2 or more. It has the features that it can be manufactured, the amount of radioactive material leached out is small, and the cost is low.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 菊池 恂 茨城県日立市幸町３丁目１番１号 株式会 社日立製作所日立工場内 (72)発明者 鈴木 脩 埼玉県熊谷市上之1100番183 (72)発明者 石橋 寛治郎 埼玉県秩父郡横瀬町大字横瀬5794番地 (56)参考文献 特開 昭59−136016（ＪＰ，Ａ) 特開 昭56−30697（ＪＰ，Ａ) 特開 昭61−250597（ＪＰ，Ａ) ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Tsuyoshi Kikuchi 3-1-1, Saiwaicho, Hitachi, Ibaraki Hitachi Ltd. Hitachi factory (72) Inventor Satoshi Suzuki, 1100, Ueno, Kumagaya, Saitama 183 (72) Inventor, Kanjiro Ishibashi, 5794, Yokoze, Yokoze-cho, Chichibu-gun, Saitama Prefecture (56) References JP-A-59-136016 (JP, A) JP-A-56-30697 (JP, A) JP-A-61- 250597 (JP, A)
Claims (1)
吸着材とを含むことを特徴とする放射性廃棄物処理用固
化材。1. A solidifying material for treating radioactive waste, which comprises a solidifying material, a foaming material, and a radioactive substance adsorbing material.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60269515A JPH0677073B2 (en) | 1985-12-02 | 1985-12-02 | Solidification material for radioactive waste treatment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60269515A JPH0677073B2 (en) | 1985-12-02 | 1985-12-02 | Solidification material for radioactive waste treatment |
Publications (3)
| Publication Number | Publication Date |
|---|---|
| JPS62142298A JPS62142298A (en) | 1987-06-25 |
| JPH0666173B2 JPH0666173B2 (en) | 1994-08-24 |
| JPH0677073B2 true JPH0677073B2 (en) | 1994-09-28 |
Family
ID=17473478
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60269515A Expired - Fee Related JPH0677073B2 (en) | 1985-12-02 | 1985-12-02 | Solidification material for radioactive waste treatment |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0677073B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01118800A (en) * | 1987-11-02 | 1989-05-11 | Touden Kankyo Eng Kk | Solidifying material for treatment of radioactive waste |
| JP2792694B2 (en) * | 1989-12-12 | 1998-09-03 | エスケ−化研株式会社 | Coating device |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5630697A (en) * | 1979-08-22 | 1981-03-27 | Mitsubishi Heavy Ind Ltd | Method and device for filling and sealing container for radioactive liquid waste |
| JPS59136016A (en) * | 1983-01-24 | 1984-08-04 | 財団法人 電力中央研究所 | Low heat resistance buried material for underground cable |
| JPS60104305A (en) * | 1983-11-11 | 1985-06-08 | 鹿島建設株式会社 | Method of reducing friction between cement group cured substance and body |
| JPS61250597A (en) * | 1985-04-30 | 1986-11-07 | 株式会社日立製作所 | Method of solidifying radioactive waste |
-
1985
- 1985-12-02 JP JP60269515A patent/JPH0677073B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPS62142298A (en) | 1987-06-25 |
| JPH0666173B2 (en) | 1994-08-24 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| R250 | Receipt of annual fees |
Free format text: JAPANESE INTERMEDIATE CODE: R250 |
|
| LAPS | Cancellation because of no payment of annual fees |