JPS61191999A - Method of stabilizing and treating uranium slag or uranium smelting waste slag - Google Patents
Method of stabilizing and treating uranium slag or uranium smelting waste slagInfo
- Publication number
- JPS61191999A JPS61191999A JP60030236A JP3023685A JPS61191999A JP S61191999 A JPS61191999 A JP S61191999A JP 60030236 A JP60030236 A JP 60030236A JP 3023685 A JP3023685 A JP 3023685A JP S61191999 A JPS61191999 A JP S61191999A
- Authority
- JP
- Japan
- Prior art keywords
- uranium
- slag
- stabilizing
- precipitate
- amount
- 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
Landscapes
- 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】
〔産業上の利用分野〕
本発明は、ウラン鉱滓又はウラン製錬廃滓の安定処理方
法の改良に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to an improvement in a method for stably treating uranium slag or uranium smelting slag.
従来より、ウラン製錬の廃液処理から発生する沈殿物は
低レベル放射性廃棄物の対象とならないため、中和処理
を施した後、スラリーの形で鉱滓ダム（貯留池）に送ら
れて保管されていた。また、ウラン鉱石浸出残液につい
ても中和処理を施した後、再度、上申に埋設し、必要な
覆土等を行い処理しているものである。Conventionally, precipitates generated from waste liquid treatment in uranium smelting are not considered low-level radioactive waste, so after being neutralized, they are sent to a tailings dam (storage pond) in the form of slurry and stored. was. In addition, the residual liquid from uranium ore leaching is also neutralized, then buried in the pit again, covered with the necessary soil, etc., and treated.
しかしながら、このような従来のウラン鉱滓又はウラン
製錬廃滓の安定処理方法にあっては、ウラン鉱滓、ウラ
ン製錬廃滓からの放射能の流出を防ぐため、鉱山操業休
止後にあっても相当長期間に亘り、モニタリング、補強
等の維持管理を行う必要があり、安定処理のためにコス
トが嵩むと共に処理作業が極めて煩雑である、という欠
点が存していた。However, in such a conventional stable treatment method for uranium slag or uranium smelting slag, in order to prevent the leakage of radioactivity from uranium slag or uranium smelting slag, a considerable amount of time is required even after mine operations have ceased. The disadvantages are that maintenance such as monitoring and reinforcement must be carried out over a long period of time, and that the cost for stable treatment increases and the treatment work is extremely complicated.
そこで本発明の目的は、処理作業コストを低減できると
共に極めて容易に実施することが可能なウラン鉱滓又は
ウラン製錬廃滓の安定処１方法を提供することにある。SUMMARY OF THE INVENTION Therefore, an object of the present invention is to provide a method for stabilizing uranium slag or uranium smelting slag, which can reduce the cost of processing operations and is extremely easy to implement.
かかる目的を達成するため１本発明にあっては放射性核
種を含有するウラン鉱滓又はウラン製錬廃滓に、モンモ
リロナイト系、カオリン系、イライト系、バーミキュラ
イト系等の粘土又は粘土鉱物のうち少なくとも一種を混
合させ、その後セメント系安定材を混合させるものであ
る。In order to achieve this object, 1 the present invention adds at least one type of clay or clay mineral such as montmorillonite, kaolin, illite, or vermiculite to uranium slag or uranium smelting slag containing radionuclides. This is followed by mixing with a cement-based stabilizer.
以下、本発明を沈殿物単体、沈殿物及びウラン鉱石浸出
残渣の混合物の各々の処理に適用した場合を例に採り説
明する。Hereinafter, the present invention will be explained by taking as an example a case in which the present invention is applied to treatment of a single precipitate and a mixture of a precipitate and a uranium ore leaching residue.
（１）沈殿物単体の処理の場合
放射性核種を含有すると共に含水比３００％以下の沈殿
物（Ｒａ ： ５００ ｐｃｉ／ｇ、Ｕ ： １ ｍｇ
／ｇ）に粘土鉱物としてのベントナイトを加え、さらに
、セメント系安定材を加えたものである。(1) In the case of treatment of single precipitate, precipitate that contains radionuclides and has a water content of 300% or less (Ra: 500 pci/g, U: 1 mg
/g), added with bentonite as a clay mineral, and further added with a cement-based stabilizer.
この場合、セメント系安定材の添加量と圧縮強度の大き
さとの関係は、−次間数の関係にあり、添加量は沈殿物
ｌＯＯ％を基準として１０％以上が効果的である。また
沈殿物の含水比は３００％以下が適切であり、粘土鉱物
の添加量は沈殿物１００％を基準として５〜１０％の範
囲である場合には圧縮強度には影響がないことが判明し
た。さらに、粘土鉱物の添加量は透水係数の観点からは
５％以下が適切であることも判明した。尚、以Ｆ′に未
実施例における配合例を示す。In this case, the relationship between the amount of cement stabilizer added and the magnitude of the compressive strength is a negative number relationship, and it is effective to add the amount of 10% or more based on 100% of the precipitate. It was also found that the appropriate water content ratio of the precipitate is 300% or less, and that if the amount of clay mineral added is in the range of 5 to 10% based on 100% precipitate, there is no effect on compressive strength. . Furthermore, it has been found that the appropriate amount of clay mineral added is 5% or less from the viewpoint of hydraulic conductivity. Incidentally, below F' shows a formulation example in an unexamined example.
中和沈殿物配合表
（２）沈殿物及びウラン鉱石浸出残渣の処理の場合放射
性核種を含有する沈殿物（Ｒａ ：５００ ｐｃｉ／ｇ
、Ｕ ： １ ｍｇ／ｇ）及び放射性核種を含有するウ
ラン鉱石浸出残渣（Ｒａ ： ４００ ｐｃｉ／ｇ。Neutralized Precipitate Mixture Table (2) In the case of treatment of precipitates and uranium ore leaching residues Precipitates containing radionuclides (Ra: 500 pci/g
, U: 1 mg/g) and uranium ore leaching residue containing radionuclides (Ra: 400 pci/g.
Ｕ：０．５■ｇ／ ｇ）に粘土鉱物としてのベントナイ
トを加え、さらにセメント系安定材を加えたものである
。Bentonite as a clay mineral is added to U: 0.5 g/g), and a cement-based stabilizer is further added.
この場合、圧縮強度については、沈殿物、セメント系安
定材の添加量が大きく影響し、ウラン鉱石浸出残渣１０
０％を基準として（以下同様）、沈殿物の添加量は１０
％〜３０％が良好であり、セメント系安定材は７．５〜
ｌＯ％が好適である。また上記ベントナイトの添加量は
５〜２０％の場合には圧縮強度に影響を及ぼさないが、
透水係数には影響を及ぼすこととなる。さらに、セメン
ト系安定材の添加量が１２．５％以下の場合には透水係
数に影響を及ぼさない。また、沈殿物の添加量は少ない
程良好であるが、３０％以下であれば良好な結果が得ら
れるものである。In this case, the compressive strength is greatly influenced by the amount of precipitate and cement stabilizer added, and the uranium ore leaching residue 10
Based on 0% (the same applies below), the amount of precipitate added is 10
% to 30% is good, and cement-based stabilizers are 7.5 to 30%.
lO% is preferred. In addition, when the amount of bentonite added is 5 to 20%, it does not affect the compressive strength, but
This will affect the hydraulic conductivity. Furthermore, if the amount of cement stabilizer added is 12.5% or less, it does not affect the hydraulic conductivity. Further, the smaller the amount of the precipitate added, the better, but good results can be obtained if the amount is 30% or less.
尚、本実施例における配合例を以下に示す。Incidentally, a formulation example in this example is shown below.
沈殿物とウラン鉱石浸出残渣の混合物配合表従って、上
記各実施例における沈殿物及び沈殿物とウラン鉱石浸出
残渣の混合物の、上記各実施例における範囲内での配合
による処理を行った結果、放射性核種の浸出性が１Ｏ−
９ＪＬＣｉ／ｍｌ以下であり、良好に核種の固定化が成
されていることが判明した。また、保水性に関しては、
ＰＦ４ 、２〜４．６の値であり、植物の根毛が利用
できる有効水分外となり、植物の根毛による水を媒体と
した放射性核種の移動を防止することができた、さらに
、ウラン鉱石残渣上に本発明に係る安定化処理層を設け
ることにより例えば１ｍ厚の頁岩覆土層と比較しＲｎガ
ス放出量は約１７１５に減少する。従って、魔法処分場
表面に本発明に係る安定化処理層を設けることにより、
著しくＲｎ放出量の低減を図ることが可能となった。さ
らに、ウラン魔法ダムを設けることなくウラン鉱滓又は
ウラン製錬魔法を安定処理することができ、処理作業の
コストを大幅に低減することが可能となった。Mixture table of precipitate and uranium ore leaching residue Accordingly, as a result of processing the precipitate and the mixture of the precipitate and uranium ore leaching residue in each of the above embodiments within the range of each of the above embodiments, radioactive The leachability of the nuclide is 1O-
It was found that the nuclide was well immobilized, with a value of 9 JLCi/ml or less. In addition, regarding water retention,
PF4 was a value of 2 to 4.6, which means that the plant root hairs were outside of the available available water, and it was possible to prevent the transfer of radionuclides by the plant root hairs through the water medium. By providing the stabilization treatment layer according to the present invention, the amount of Rn gas released is reduced to about 1715 compared to, for example, a 1 m thick shale covering layer. Therefore, by providing the stabilizing layer according to the present invention on the surface of the magical disposal site,
It has become possible to significantly reduce the amount of Rn released. Furthermore, it is possible to stably process uranium slag or uranium smelting magic without installing a uranium magic dam, making it possible to significantly reduce the cost of processing work.
本発明は以上のような構成を有することから、ウラン鉱
滓又はウラン製錬魔法の処理にあたり、従来のように鉱
山操業休止後も長期間に亘って維持管理を行う必要がな
くなり、無管理状態で処分することが可能となるため、
従来よりも処理作業コストを大幅に低減することが可能
となると共に容易に処理作業を行うことができる、とい
う効果を奏する。Since the present invention has the above-described configuration, when processing uranium slag or uranium smelting magic, there is no need for maintenance and management for a long period of time even after mine operations have ceased, unlike in the past, and the process can be carried out in an unmanaged state. Since it is possible to dispose of
It is possible to significantly reduce the cost of processing work compared to the conventional method, and the processing work can be performed easily.
Claims (1)
、モンモリロナイト系、カオリン系、イライト系、バー
ミキュライト系等の粘土又は粘土鉱物のうち少なくとも
一種を混合させ、その後セメント系安定材を混合させる
ことにより、ウラン鉱滓又はウラン製錬廃滓を安定処理
する方法。By mixing at least one type of clay or clay mineral such as montmorillonite, kaolin, illite, or vermiculite with uranium slag or uranium smelting slag containing radionuclides, and then mixing with a cement-based stabilizer. , a method for stably processing uranium slag or uranium smelting slag.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60030236A JPS61191999A (en) | 1985-02-20 | 1985-02-20 | Method of stabilizing and treating uranium slag or uranium smelting waste slag |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60030236A JPS61191999A (en) | 1985-02-20 | 1985-02-20 | Method of stabilizing and treating uranium slag or uranium smelting waste slag |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS61191999A true JPS61191999A (en) | 1986-08-26 |
Family
ID=12298077
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60030236A Pending JPS61191999A (en) | 1985-02-20 | 1985-02-20 | Method of stabilizing and treating uranium slag or uranium smelting waste slag |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61191999A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0868895A (en) * | 1994-08-29 | 1996-03-12 | Hitachi Ltd | Solidification method and device for radioactive waste |
| JP2013174538A (en) * | 2012-02-27 | 2013-09-05 | Hisashi Nirei | Decontamination method of geological contamination by radioactive substances |
| CN111689701A (en) * | 2020-06-19 | 2020-09-22 | 中山大学 | Electric furnace steel slag-based cement admixture or concrete admixture, preparation method and application |
| CN111689700A (en) * | 2020-06-19 | 2020-09-22 | 中山大学 | Waste-utilizing environment-friendly high-early-strength fast-hardening cementing material and preparation method thereof |
| US11978568B1 (en) * | 2022-11-18 | 2024-05-07 | The Fourth Research And Design Engineering Institute Of China National Nuclear Corporation | Method for stabilizing neutralization slag of uranium associated zirconium and zirconia, and stabilization agent used therein |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS547100A (en) * | 1977-06-10 | 1979-01-19 | Kernforschungsz Karlsruhe | Method of solidifying radioactive waste |
| JPS55151299A (en) * | 1979-05-02 | 1980-11-25 | British Nuclear Fuels Ltd | Plutonium waste fixation |
-
1985
- 1985-02-20 JP JP60030236A patent/JPS61191999A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS547100A (en) * | 1977-06-10 | 1979-01-19 | Kernforschungsz Karlsruhe | Method of solidifying radioactive waste |
| JPS55151299A (en) * | 1979-05-02 | 1980-11-25 | British Nuclear Fuels Ltd | Plutonium waste fixation |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0868895A (en) * | 1994-08-29 | 1996-03-12 | Hitachi Ltd | Solidification method and device for radioactive waste |
| JP2013174538A (en) * | 2012-02-27 | 2013-09-05 | Hisashi Nirei | Decontamination method of geological contamination by radioactive substances |
| CN111689701A (en) * | 2020-06-19 | 2020-09-22 | 中山大学 | Electric furnace steel slag-based cement admixture or concrete admixture, preparation method and application |
| CN111689700A (en) * | 2020-06-19 | 2020-09-22 | 中山大学 | Waste-utilizing environment-friendly high-early-strength fast-hardening cementing material and preparation method thereof |
| US11978568B1 (en) * | 2022-11-18 | 2024-05-07 | The Fourth Research And Design Engineering Institute Of China National Nuclear Corporation | Method for stabilizing neutralization slag of uranium associated zirconium and zirconia, and stabilization agent used therein |
| US20240170173A1 (en) * | 2022-11-18 | 2024-05-23 | The Fourth Research And Design Engineering Institute Of China National Nuclear Corporation | Method for stablizing neutralization slag of uranium associated zirconium and zirconia, and stablization agent used therein |
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