JPS58219500A - Method of solidfying radioactive liquid waste - Google Patents

Method of solidfying radioactive liquid waste

Info

Publication number
JPS58219500A
JPS58219500A JP10222282A JP10222282A JPS58219500A JP S58219500 A JPS58219500 A JP S58219500A JP 10222282 A JP10222282 A JP 10222282A JP 10222282 A JP10222282 A JP 10222282A JP S58219500 A JPS58219500 A JP S58219500A
Authority
JP
Japan
Prior art keywords
waste liquid
radioactive waste
cesium
tetravalent metal
gel
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
JP10222282A
Other languages
Japanese (ja)
Inventor
直人 植竹
河村 文雄
菊池 恂
深沢 哲生
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP10222282A priority Critical patent/JPS58219500A/en
Publication of JPS58219500A publication Critical patent/JPS58219500A/en
Pending legal-status Critical Current

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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、放射性廃液のガラス固化方法に係り、特に高
レベル放射性廃液に好適なガラス固化方法に関するもの
である。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for vitrifying radioactive waste liquid, and particularly to a vitrification method suitable for high-level radioactive waste liquid.

従来のガラス固化方法では、廃液とガラスフリットを混
合して加熱溶融するため、1000°C〜1300°C
の高温が必要になり、セシウムの揮発が問題となる。
In the conventional vitrification method, the waste liquid and glass frit are mixed and melted by heating, so the temperature is 1000°C to 1300°C.
This requires high temperatures, and volatilization of cesium becomes a problem.

本発明の目的は、セシウム等の廃液中の揮発成分の揮発
を抑制して、安定にガラス固化体中に閉じ込める方法を
提供することにある。
An object of the present invention is to provide a method for suppressing the volatilization of volatile components such as cesium in a waste liquid and stably confining them in a vitrified body.

4価金属の酸性塩はナトリウムからセシウムまでのアル
カリ金属イオンを吸着する。これらの4価金属の酸性塩
は、4価金属の可溶性塩と酸を加えることにより、容易
にゲル状で得ることができる。しかも4価金属は、ガラ
スの網目構造形成イオンとなり、容易にガラス構造中に
取り込まれる。
Acidic salts of tetravalent metals adsorb alkali metal ions from sodium to cesium. These acidic salts of tetravalent metals can be easily obtained in gel form by adding soluble salts of tetravalent metals and acids. Moreover, the tetravalent metal becomes an ion that forms the network structure of the glass and is easily incorporated into the glass structure.

それ故に、ゲル状の4価金属の酸性塩に廃液中のセシウ
ムを吸着させたのち、ゲル化したケイ酸す) IJウム
と混合して熱処理すると容易にガラス化することができ
、しかも反応物が両方ともゲル状であるため反応性も良
い。この結果、4価金属の酸性塩に吸着されたセシウム
は、揮発せず、ガラス中に取り込まれるので、セシウム
の揮発が抑制される。
Therefore, after adsorbing cesium in the waste liquid to a gelatinous acid salt of a tetravalent metal, it can be easily vitrified by mixing it with gelled silicic acid (IJ) and heat-treating it. Both have good reactivity because they are gel-like. As a result, the cesium adsorbed on the acid salt of the tetravalent metal does not volatilize and is taken into the glass, so that volatilization of the cesium is suppressed.

以下、本発明の一実施例を第1図により説明する。セシ
ウム吸着のための4価金属の酸性塩として、セシウムに
対して強い選択性を持つリン酸チタンを使用する。核燃
料再処理施設からの高レベル廃液を固化する場合、廃液
中には1〜l0WIのセシウムが含まれる。セシウムを
過剰に見積って10W−L−チ含まれていると考えると
、廃液1kg中には0.75モルのセシウムが含まれて
いる。リン酸チタンの交換容量は7.5 meq/g 
 で、廃液1kgを処理するのに100gのリン酸チタ
ンが必要となる。
An embodiment of the present invention will be described below with reference to FIG. Titanium phosphate, which has strong selectivity for cesium, is used as an acid salt of a tetravalent metal for cesium adsorption. When solidifying high-level waste liquid from a nuclear fuel reprocessing facility, the waste liquid contains 1 to 10 WI of cesium. If we assume that cesium is overestimated and contains 10 W-L-H, then 0.75 mol of cesium is contained in 1 kg of waste liquid. The exchange capacity of titanium phosphate is 7.5 meq/g
Therefore, 100g of titanium phosphate is required to treat 1kg of waste liquid.

高レベル廃液タンク1に貯蔵された高レベル廃液は、吸
着剤タンク3に貯蔵されたリン酸チタンゲルと混合され
たのち、混合機4に供給され、ケイ酸ソーダ貯蔵タンク
2に貯蔵されたケイ酸ソーダ溶液及び添加剤タンク4に
貯蔵されたホウ酸と1111″ 混合され、ゲル状となる。生成したゲル状物質は乾燥機
5に供給され、乾燥用ヒーター6により200°C〜3
00°Cで加熱乾燥された後、溶融炉7に送られ、溶融
用ヒーター8により1000°C〜1100°Cで加熱
溶融され、キャニスタ−9に入れられた後、冷却固化さ
れる。
The high-level waste liquid stored in the high-level waste liquid tank 1 is mixed with the titanium phosphate gel stored in the adsorbent tank 3, and then supplied to the mixer 4, and the silicic acid stored in the sodium silicate storage tank 2 is mixed with the titanium phosphate gel stored in the adsorbent tank 3. The soda solution and the boric acid stored in the additive tank 4 are mixed at 1111" to form a gel. The gel-like substance produced is supplied to a dryer 5 and heated to 200°C to 300°C by a drying heater 6.
After being heated and dried at 00°C, it is sent to a melting furnace 7, heated and melted by a melting heater 8 at 1000°C to 1100°C, placed in a canister 9, and then cooled and solidified.

本方法によると、セシウムがリン酸チタンに吸着された
状態で加熱されるため、セシウムの揮発が抑制されるほ
か、ガラス原料がゲル状態であるため、反応性が良く比
較的低温で溶融できるため、装置材料の耐久性の問題が
低減される。また、ゲル状物質を生成して、乾燥を行う
ため、従来のガラス固化装置で問題となっている粉体取
り扱いの問題がほとんど生じない。
According to this method, cesium is heated while adsorbed on titanium phosphate, which suppresses the volatilization of cesium, and since the glass raw material is in a gel state, it has good reactivity and can be melted at a relatively low temperature. , durability problems of device materials are reduced. In addition, since a gel-like substance is generated and dried, there are almost no problems in handling powder, which are problems in conventional vitrification equipment.

本発明によれば、セシウムを吸着させた状態で熱処理を
行ない、ガラス化することができるためセシウムの揮発
を防いで、セシウムを安定にガラス固化体中に閉じ込め
ることができる。
According to the present invention, heat treatment can be performed and vitrification can be performed in a state in which cesium is adsorbed, so that volatilization of cesium can be prevented and cesium can be stably confined in the vitrified body.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は本発明による放射性廃液ガラス固化装置1 置の概念図である。 1・・・高レベル廃液貯蔵タンク、2・・・ケイ酸ソー
ダ貯蔵タンク、3・・・吸着剤貯蔵タンク、4・・・添
加剤貯蔵タンク、5・・・乾燥機、6・・・乾燥用ヒー
ター、7・・・溶融炉、8・・・溶融用ヒーター、9・
・・キャニスタ−0 第 1 口
FIG. 1 is a conceptual diagram of a radioactive waste liquid vitrification apparatus according to the present invention. 1...High level waste liquid storage tank, 2...Soda silicate storage tank, 3...Adsorbent storage tank, 4...Additive storage tank, 5...Dryer, 6...Drying heater for use, 7...melting furnace, 8...heater for melting, 9.
・Canister-0 1st opening

Claims (1)

【特許請求の範囲】 1、水溶液状の放射性廃液を固化する方法において、放
射性廃液にゲル状の4価金属の酸性塩、ケイ酸ナトリウ
ム水溶液、ケイ酸ナトリウムゲル化剤及びガラス安定化
のための添加剤を加えてゲル状沈殿とした後、これを熱
処理してガラス化することを特徴とする放射性廃液固化
方法。 2、特許請求の範囲第1項において、放射性廃液に4価
金属の酸性塩を添加する代わりに、4価金属の可溶性塩
とリン酸を加えることを特徴とする放射性廃液固化方法
。 3、特許請求の範囲第1項において、4価金属の酸性塩
としてリン酸チタンを用いることを特徴とする放射性廃
液固化方法。
[Claims] 1. A method for solidifying radioactive waste liquid in the form of an aqueous solution, in which the radioactive waste liquid contains a gel-like acid salt of a tetravalent metal, an aqueous sodium silicate solution, a sodium silicate gelling agent, and a glass stabilizing agent. A radioactive waste liquid solidification method characterized by adding an additive to form a gel-like precipitate and then heat-treating the precipitate to vitrify it. 2. A radioactive waste liquid solidification method according to claim 1, characterized in that instead of adding an acid salt of a tetravalent metal to the radioactive waste liquid, a soluble salt of a tetravalent metal and phosphoric acid are added to the radioactive waste liquid. 3. A radioactive waste liquid solidification method according to claim 1, characterized in that titanium phosphate is used as the acid salt of a tetravalent metal.
JP10222282A 1982-06-16 1982-06-16 Method of solidfying radioactive liquid waste Pending JPS58219500A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP10222282A JPS58219500A (en) 1982-06-16 1982-06-16 Method of solidfying radioactive liquid waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP10222282A JPS58219500A (en) 1982-06-16 1982-06-16 Method of solidfying radioactive liquid waste

Publications (1)

Publication Number Publication Date
JPS58219500A true JPS58219500A (en) 1983-12-20

Family

ID=14321633

Family Applications (1)

Application Number Title Priority Date Filing Date
JP10222282A Pending JPS58219500A (en) 1982-06-16 1982-06-16 Method of solidfying radioactive liquid waste

Country Status (1)

Country Link
JP (1) JPS58219500A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1984004624A1 (en) * 1983-05-18 1984-11-22 Hitachi Ltd Process for solidifying radioactive wastes
JPS61176893A (en) * 1985-02-01 1986-08-08 株式会社日立製作所 Method of solidifying radioactive contaminated organic liquid waste
JP2014215269A (en) * 2013-04-30 2014-11-17 水ing株式会社 Method for treating wastewater containing radioactive cesium

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1984004624A1 (en) * 1983-05-18 1984-11-22 Hitachi Ltd Process for solidifying radioactive wastes
JPS61176893A (en) * 1985-02-01 1986-08-08 株式会社日立製作所 Method of solidifying radioactive contaminated organic liquid waste
JP2014215269A (en) * 2013-04-30 2014-11-17 水ing株式会社 Method for treating wastewater containing radioactive cesium

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