JPS60168097A - Method of treating liquefied radioactive waste - Google Patents

Method of treating liquefied radioactive waste

Info

Publication number
JPS60168097A
JPS60168097A JP2298584A JP2298584A JPS60168097A JP S60168097 A JPS60168097 A JP S60168097A JP 2298584 A JP2298584 A JP 2298584A JP 2298584 A JP2298584 A JP 2298584A JP S60168097 A JPS60168097 A JP S60168097A
Authority
JP
Japan
Prior art keywords
radioactive waste
waste
water
cement
silica
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
Application number
JP2298584A
Other languages
Japanese (ja)
Inventor
直 岡本
宇都宮 透
正典 樋口
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.)
Mitsui Construction Co Ltd
Original Assignee
Mitsui Construction Co Ltd
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.)
Filing date
Publication date
Application filed by Mitsui Construction Co Ltd filed Critical Mitsui Construction Co Ltd
Priority to JP2298584A priority Critical patent/JPS60168097A/en
Publication of JPS60168097A publication Critical patent/JPS60168097A/en
Pending legal-status Critical Current

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  • 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】 (イ)産業上の利用分野 原子力発電所や核燃料再処理工場、原子力研究所などか
ら出るトリヂウム廃棄物等の低レベル又は中レベルの液
体状放射性廃棄物は今後益々増加することが予想される
[Detailed description of the invention] (a) Industrial application field Low-level or medium-level liquid radioactive waste such as tridium waste generated from nuclear power plants, nuclear fuel reprocessing plants, nuclear power research institutes, etc. will continue to increase in the future. It is expected that

本発明は、これら液体状放射性廃棄物の処理方法に関す
るものである。
The present invention relates to a method for disposing of these liquid radioactive wastes.

(ロ)従来技術 この種の液体状放射性廃棄物の管理方法としては、各種
の方法が提案され一部は実施されているが、最も一般的
な方法としてはこれを固化体どしてドラム缶等の容器に
詰めた状態で栴内に保管している。
(B) Prior art Various methods have been proposed for managing this type of liquid radioactive waste, some of which have been implemented, but the most common method is to solidify it into a drum or other container. It is stored in a container inside the shrine.

又、低レベルの廃棄物に関しては、固化体としたものを
容器に密封して深海底に沈める方法も現在検討されてい
る。
Regarding low-level waste, a method of solidifying the waste, sealing it in a container, and sinking it into the deep seabed is currently being considered.

前記固化体にする方法としては、現在迄のところ次のよ
うなものがある。
As methods for forming the solidified material, the following methods are currently available.

■ポルトランドセメント等を使用したセメント固化体。■Cement solidification using Portland cement, etc.

■ポリマー含浸等によるセメント固化体。■Cement solidified by polymer impregnation, etc.

■アスファルト固化体。■Asphalt solidification.

■ポリマー同化体。■Polymer assimilate.

しかしながら、上記■のセメント固化体の場合、単に練
り混ぜをするだけの簡単な処理(゛すむが、練り混ぜを
行うための理論水和量以上の水分が必要であり、余剰な
水分の移動と、その水分が占めていた空隙のために低浸
出率の固化体が得られない欠員があった。
However, in the case of solidified cement as described in (2) above, a simple process of simply kneading and mixing is possible, but the kneading requires more water than the theoretical hydration amount, and the movement of excess water is difficult. , there was a vacancy where a solidified material with a low leaching rate could not be obtained due to the voids occupied by the water.

又、上記■、■、■の各固化体の場合、単に練り混ぜを
するだけの簡単な処理ではすまないために、作業手順が
複雑で設備も大掛りになる欠点があつlC0 更に上記■、■の固化体の場合、水の化学形をとるトリ
チウム廃棄物が水和しにくい欠点もあった。
In addition, in the case of each of the solidified materials mentioned above, it is not enough to simply knead and mix, so there are drawbacks such as complicated work procedures and large-scale equipment. In the case of the solidified material (2), there was also the drawback that tritium waste, which takes the chemical form of water, is difficult to hydrate.

(ハ)発明の目的 そこで本願発明は前記従来技術の欠点を改善するもので
あり、単に練り混ぜるだ番ノの簡I11な処理でしかも
余剰水なしで練り混ぜることが可能な固化体として、ト
リチウム廃棄物等の液体状11i躬性廃棄物を処理する
ことができる処理方法の提供を目的とするものである。
(c) Purpose of the Invention Therefore, the present invention aims to improve the drawbacks of the prior art described above, and uses tritium as a solidified material that can be kneaded and mixed with a simple process other than simply kneading and without excess water. The object of the present invention is to provide a processing method capable of processing liquid waste such as waste.

(ニ)発明の構成 液体状放射性廃棄物に、少くともセメントと、シリカフ
ニームを主成分とづる高強度混和剤を混合して固化体と
した処理方法である。
(d) Constituent structure of the invention This is a treatment method in which liquid radioactive waste is mixed with at least cement and a high-strength admixture whose main components are silica hneem to solidify it.

(ホ)実施例 本願発明に使用されるシリカフニームは、フェロシリコ
ンおよびシリコンメタルを1−1を気かで製造するに際
し、石炭と^純度石英の還元反応によって生ずる一種の
産業廃棄物である。
(E) Example The silica neem used in the present invention is a type of industrial waste produced by the reduction reaction between coal and high-purity quartz when ferrosilicon and silicon metal are produced in air.

該シリカッ2.−ムは二酸化珪素(SiO2)主成分と
した微粉末(酋通しメントの50〜60倍の粉末度)で
あって、単位容積重量がセメントの1/4〜115程度
である。従ってセメントの混和剤としてシリカフコーム
を混合すると、単位セメント量は低減され、且つ同じス
ランプを得るのに必要な水石は増加づ゛るので余剰水が
なくなる。
The silica2. -mu is a fine powder mainly composed of silicon dioxide (SiO2) (50 to 60 times the fineness of the powdered cement), and its unit volume weight is about 1/4 to 115 times that of cement. Therefore, when silica fucomb is mixed as an admixture for cement, the unit amount of cement is reduced, and the amount of water stone required to obtain the same slump increases, so that surplus water is eliminated.

本実施例では、セメント100重量部、シリカフコーム
2.5rAm部にトリチウム水25重邑部を加えて練り
混ぜて固化体としたものである。
In this example, 100 parts by weight of cement, 2.5 parts by weight of silica fucomb, and 25 parts by weight of tritium water were added and mixed to form a solidified product.

これにより、余剰水なしで混練りがおこなわれ、余剰水
の移動や余剰水によって占められる空隙は見られず、浸
出率の低い固化体が得られた。
As a result, kneading was carried out without surplus water, and no movement of surplus water or voids occupied by surplus water was observed, and a solidified material with a low leaching rate was obtained.

又強度を向上させるために、高性能減水剤を混和剤とし
て加えるとより効果的である。
Also, in order to improve the strength, it is more effective to add a high performance water reducing agent as an admixture.

(へ)発明の効果 上記実施例のとおり、本願発明ではシリカフニームの性
状を生かして、単に混練りするだけで余剰水がなく、浸
出率の少ない固化体としてトリチウム水等の低レベルあ
るいは中レベルの液体状放射性廃棄物を71(即づるこ
とができると共に、産業廃棄物の一種であるシリカフニ
ームの有効活町°を計るものである。
(F) Effects of the Invention As shown in the above embodiments, the present invention takes advantage of the properties of silica hneem and uses low or medium level tritiated water as a solidified material with a low leaching rate by simply kneading without producing excess water. It is possible to collect 71% of liquid radioactive waste and measure the effective utilization of silica, a type of industrial waste.

\ 、+□/\ 、+□/

Claims (1)

【特許請求の範囲】[Claims] 液体状放射性廃棄物に、少くともレメントと、シリカフ
ニームを主成分とする高強度混和剤を混合し、前記液体
状放射性廃棄物を固化せしめたことを特徴とする液体状
放射性廃棄物の処理方法。
A method for disposing of liquid radioactive waste, characterized in that the liquid radioactive waste is solidified by mixing at least Lement and a high-strength admixture mainly composed of silica hneem.
JP2298584A 1984-02-13 1984-02-13 Method of treating liquefied radioactive waste Pending JPS60168097A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2298584A JPS60168097A (en) 1984-02-13 1984-02-13 Method of treating liquefied radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2298584A JPS60168097A (en) 1984-02-13 1984-02-13 Method of treating liquefied radioactive waste

Publications (1)

Publication Number Publication Date
JPS60168097A true JPS60168097A (en) 1985-08-31

Family

ID=12097834

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2298584A Pending JPS60168097A (en) 1984-02-13 1984-02-13 Method of treating liquefied radioactive waste

Country Status (1)

Country Link
JP (1) JPS60168097A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109529248A (en) * 2018-11-27 2019-03-29 云南省环境科学研究院(中国昆明高原湖泊国际研究中心) A kind of stabilizer and preparation method thereof for handling arsenic-containing waste residue

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109529248A (en) * 2018-11-27 2019-03-29 云南省环境科学研究院(中国昆明高原湖泊国际研究中心) A kind of stabilizer and preparation method thereof for handling arsenic-containing waste residue

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