JP2000346994A - Synthesizing method of sodalite type radioactive waste solidified body - Google Patents
Synthesizing method of sodalite type radioactive waste solidified bodyInfo
- Publication number
- JP2000346994A JP2000346994A JP11156506A JP15650699A JP2000346994A JP 2000346994 A JP2000346994 A JP 2000346994A JP 11156506 A JP11156506 A JP 11156506A JP 15650699 A JP15650699 A JP 15650699A JP 2000346994 A JP2000346994 A JP 2000346994A
- Authority
- JP
- Japan
- Prior art keywords
- sodalite
- radioactive waste
- solidified
- halide
- type radioactive
- 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.)
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- Silicates, Zeolites, And Molecular Sieves (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は使用済み核燃料の再
処理施設から発生する核分裂生成物を含む放射性廃棄物
の固化体を合成する方法に関する。更に詳しくはＩ−１
２９等のヨウ素のようなハロゲン化物を固定するソーダ
ライト型放射性廃棄物の固化体の合成方法に関するもの
である。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for synthesizing solidified radioactive waste containing fission products generated from a spent nuclear fuel reprocessing facility. More specifically, I-1
The present invention relates to a method for synthesizing a solidified sodalite-type radioactive waste for fixing a halide such as iodine such as 29.
【０００２】[0002]
【従来の技術】一般に使用済み核燃料再処理施設から発
生する核分裂生成物を含む放射性廃棄物に対してはガラ
ス中に固定化し処分する技術が確立している。このガラ
ス固化放射性廃棄物固化体は、乾式再処理法や乾式群分
離から発生する廃棄物中の塩素によりガラス化が阻害さ
れ、結果としては塩化物形態をなすこれらの廃棄物固化
体としては適していないという問題があった。またガラ
ス固化体に適する酸化物への転換を経てガラス固化体に
する方法は、塩化物から酸化物への転換が熱力学的に困
難であることと、その際に余剰となった塩素が塩素ガス
や塩化水素ガスなどの形態で発生することからその取扱
いが困難になり、プロセスが複雑になるという問題があ
った。この点を解決するため、天然に存在する鉱物の一
種で、そのアルミノケイ酸塩の三次元籠構造内にＮａＣ
ｌなどのハロゲン化物を含む長期間安定な鉱物として知
られていて、塩化物形態の放射性廃棄物の固化に対して
有効なソーダライトを用いたソーダライト型廃棄物固化
体及びその合成方法が提案されている（特開平７−２７
０５９６）。2. Description of the Related Art In general, a technology has been established in which radioactive waste containing fission products generated from a spent nuclear fuel reprocessing facility is fixed in glass and disposed of. This vitrified radioactive waste solidified product is suitable for use as a waste solidified in the form of chloride as the vitrification is inhibited by chlorine in the waste generated from the dry reprocessing method or dry group separation. There was no problem. In addition, the method of converting the oxide into a vitrified oxide suitable for the vitrified material is based on the fact that the conversion from chloride to the oxide is thermodynamically difficult, and the excess chlorine at that time is converted into chlorine. Since it is generated in the form of gas or hydrogen chloride gas, it is difficult to handle the gas and the process becomes complicated. In order to solve this problem, a kind of naturally occurring mineral, NaC is contained in the three-dimensional cage structure of the aluminosilicate.
1) A sodalite-type solidified solid using sodalite, which is known as a long-term stable mineral containing halides such as l and is effective for solidifying radioactive waste in the form of chloride, and a method for synthesizing the same. (Japanese Patent Laid-Open No. 7-27)
0596).
【０００３】この合成方法は、ＮａＯＨ、Ａｌ2 Ｏ3 、
ＳｉＯ2 を混合し６００〜９００℃で加熱して中間反応
体をあらかじめ合成し、この中間反応体とアルカリ金属
元素、アルカリ土類金属元素、希土類元素、貴金属元素
などの塩化物などのハロゲン化物と混合し６００〜９０
０℃で加熱するか、或はＮａＡｌＯ2 、ＳｉＯ2 、アル
カリ金属元素、アルカリ土類金属元素、希土類元素、貴
金属元素などの塩化物などのハロゲン化物を混合し、次
いで７００℃以上で加熱する方法である。上記方法によ
り合成された固化体は天然において塩化物を含む鉱物の
一種類であるソーダライト石と同じ三次元骨格構造によ
り核分裂生成物のハロゲン化物を保持することができ、
そのアルミノケイ酸塩のソーダライト籠構造内に保持さ
れたハロゲン化物の形態を持つ放射性廃棄物、例えば水
に溶け易いヨウ素を含む廃棄物を安定に固化することが
できる。[0003] This synthesis method uses NaOH, Al 2 O 3 ,
SiO 2 is mixed and heated at 600 to 900 ° C. to synthesize an intermediate reactant in advance, and the intermediate reactant is mixed with a halide such as a chloride such as an alkali metal element, an alkaline earth metal element, a rare earth element or a noble metal element. Mix 600-90
A method of heating at 0 ° C. or mixing halides such as chlorides such as NaAlO 2 , SiO 2 , alkali metal elements, alkaline earth metal elements, rare earth elements, and noble metal elements, and then heating at 700 ° C. or higher. It is. The solidified body synthesized by the above method can retain a fission product halide by the same three-dimensional skeleton structure as sodalite stone, which is a kind of mineral containing chloride in nature,
Radioactive waste in the form of a halide retained in the aluminosilicate sodalite basket structure, for example, waste containing water-soluble iodine, can be solidified stably.
【０００４】[0004]
【発明が解決しようとする課題】しかし、上記従来の合
成方法は高温常圧で操作されているため、ハロゲン化物
がヨウ素を含む場合には、合成中にヨウ素が揮発して飛
散するため、得られたソーダライト型放射性廃棄物固化
体中へのヨウ素の収率が低い問題がある。また合成が６
００℃以上の高温で行われ、しかも合成に２４〜７２時
間という長時間を要するため、合成装置の負担が大きく
て、エネルギーの消費量が多く、その結果、経済性に劣
る不都合がある。更に出発原料のハロゲン化物としてＡ
ｇＩ等の難溶性化合物を使用すると、目的とする放射性
廃棄物固化体の合成が困難になる問題点がある。本発明
の目的は、経済性に優れ、核分裂生成物のハロゲン化物
を高収率に固化するソーダライト型放射性廃棄物固化体
の合成方法を提供することにある。However, since the above conventional synthesis method is operated at a high temperature and a normal pressure, when the halide contains iodine, iodine is volatilized during the synthesis and scatters. There is a problem that the yield of iodine in the solidified sodalite-type radioactive waste is low. In addition, 6
Since the synthesis is performed at a high temperature of 00 ° C. or more and the synthesis requires a long time of 24 to 72 hours, the load on the synthesis apparatus is large, the energy consumption is large, and as a result, there is a disadvantage that economic efficiency is poor. Further, as a starting material halide, A
When a hardly soluble compound such as gI is used, there is a problem that it is difficult to synthesize a target solidified radioactive waste. An object of the present invention is to provide a method for synthesizing a sodalite-type radioactive waste solidified material which is excellent in economic efficiency and solidifies a fission product halide in a high yield.
【０００５】[0005]
【課題を解決するための手段】請求項１又は２に係る発
明は、ＮａＡｌＯ2、ＳｉＯ2及び核分裂生成物のハロゲ
ン化物を混合するか、又はＮａＯＨ、Ａｌ2Ｏ3、ＳｉＯ
2及び核分裂生成物のハロゲン化物を混合し、温度１２
０〜３００℃、圧力０．１〜５ＭＰａ、水の存在下で１
〜６時間水熱反応させることによりソーダライト型放射
性廃棄物固化体を得ることを特徴とするソーダライト型
放射性廃棄物固化体の合成方法である。請求項３に係る
発明は、ＮａＯＨ、カオリンを主体とする材料及び核分
裂生成物のハロゲン化物を混合し、温度８０〜３００
℃、圧力０．１〜５ＭＰａ、水の存在下で１〜６時間水
熱反応させることによりソーダライト型放射性廃棄物固
化体を得ることを特徴とするソーダライト型放射性廃棄
物固化体の合成方法である。請求項４又は５に係る発明
は、Ａｇ2Ｏ、ＳｉＯ2、Ａｌ(ＯＨ)3及び核分裂生成物
のハロゲン化物を混合するか又はＡｇ2Ｏ、ＮａＡｌ
Ｏ2、ＳｉＯ2、Ａｌ(ＯＨ)3及び核分裂生成物のハロゲ
ン化物を混合し、温度１２０〜３００℃、圧力０．１〜
５ＭＰａ、水の存在下で１〜６時間水熱反応させること
によりソーダライト型放射性廃棄物固化体を得ることを
特徴とするソーダライト型放射性廃棄物固化体の合成方
法である。請求項６に係る発明は、Ａｇ2Ｏ、カオリン
を主体とする材及び核分裂生成物のハロゲン化物を混合
し、温度８０〜３００℃、圧力０．１〜５ＭＰａ、水の
存在下で１〜６時間水熱反応させることによりソーダラ
イト型放射性廃棄物固化体を得ることを特徴とするソー
ダライト型放射性廃棄物固化体の合成方法である。According to a first or second aspect of the present invention, there is provided a method of mixing NaAlO 2 , SiO 2 and a fission product halide, or mixing NaOH, Al 2 O 3 , SiO 2
2 and the fission product halide are mixed at a temperature of 12
0-300 ° C, pressure 0.1-5MPa, 1 in the presence of water
It is a method for synthesizing a solidified sodalite-type radioactive waste, wherein a solidified sodalite-type radioactive waste is obtained by performing a hydrothermal reaction for up to 6 hours. According to a third aspect of the present invention, a material mainly composed of NaOH and kaolin and a halide of a fission product are mixed, and a temperature of 80 to 300 is mixed.
C., a pressure of 0.1 to 5 MPa, and a hydrothermal reaction in the presence of water for 1 to 6 hours to obtain a solidified sodalite-type radioactive waste, which is characterized by obtaining a solidified sodalite-type radioactive waste. It is. The invention according to claim 4 or 5 is that Ag 2 O, SiO 2 , Al (OH) 3 and a fission product halide are mixed or Ag 2 O, NaAl
O 2 , SiO 2 , Al (OH) 3 and a fission product halide are mixed at a temperature of 120 to 300 ° C. and a pressure of 0.1 to
This is a method for synthesizing a solidified sodalite-type radioactive waste, wherein a solidified sodalite-type radioactive waste is obtained by performing a hydrothermal reaction in the presence of water at 5 MPa for 1 to 6 hours. The invention according to claim 6 is a method of mixing Ag 2 O, a material mainly composed of kaolin, and a halide of a fission product at a temperature of 80 to 300 ° C., a pressure of 0.1 to 5 MPa, and a pressure of 1 to 6 in the presence of water. This is a method for synthesizing a solidified sodalite-type radioactive waste, wherein a solidified sodalite-type radioactive waste is obtained by performing a hydrothermal reaction for a time.
【０００６】請求項１〜６に係る発明によれば、０．１
〜５ＭＰａの圧力下、１２０〜３００℃又は８０〜３０
０℃のような比較的低い温度で水熱反応を行って、密閉
された水熱反応容器内でソーダライト型放射性廃棄物固
化体を合成するため、合成中にヨウ素が揮発して飛散す
るおそれは極めて少なくなり、高収率で核分裂生成物の
ハロゲン化物を固化することができる。請求項７に係る
発明は、請求項１ないし６いずれかに係る発明であっ
て、ハロゲン元素をＸとするとき、ハロゲン化物がＮａ
Ｘ、ＡｇＸ又はＸ2である合成方法である。請求項８に
係る発明は、請求項７に係る発明であって、ハロゲン元
素がヨウ素である合成方法である。According to the first to sixth aspects of the present invention, 0.1
120 ~ 300 ° C or 80 ~ 30 under pressure of ~ 5MPa
Hydrothermal reaction is performed at a relatively low temperature such as 0 ° C to synthesize solid sodalite-type radioactive waste in a sealed hydrothermal reactor. Therefore, iodine is volatilized and scattered during synthesis. It is extremely low and can solidify the fission product halide in high yield. The invention according to claim 7 is the invention according to any one of claims 1 to 6, wherein when the halogen element is X, the halide is Na
X, is a synthesis method is AgX or X 2. The invention according to claim 8 is the invention according to claim 7, which is a synthesis method in which the halogen element is iodine.
【０００７】[0007]
【発明の実施の形態】本発明の核分裂生成物のハロゲン
化物としては、ＮａＦ，ＮａＣｌ，ＮａＢｒ，ＮａＩな
どのナトリウム化合物、ＡｇＦ，ＡｇＣｌ，ＡｇＢｒ，
ＡｇＩなどの銀化合物、及びＦ2，Ｃｌ2，Ｂｒ2，Ｉ2な
どのハロゲンガスが挙げられる。BEST MODE FOR CARRYING OUT THE INVENTION As the halide of the fission product of the present invention, sodium compounds such as NaF, NaCl, NaBr and NaI, AgF, AgCl, AgBr,
Silver compounds such as AgI; and halogen gases such as F 2 , Cl 2 , Br 2 , and I 2 .
【０００８】ハロゲン化物は，ＡｇＡｌＳｉＯ4、（Ｎ
ａＡｌＳｉＯ4）6・２ＭＸ等のソーダライト型の化合物
の形態で固化される。ここでＭＸはハロゲン化物を表
し、Ｘはハロゲン元素を、ＭはＮａ、Ｓｒ、Ａｇ、Ｃ
ｓ、Ｂａ等の金属元素を意味する。固化物の合成反応は
核分裂生成物のハロゲン化物を含む化合物等を水熱反応
することにより行われる。この合成反応を促進するため
に、ハロゲン化物を含む混合物は圧縮固化してペレット
状で行われることが好ましい。The halide is AgAlSiO 4 , (N
is solidified in the form of aAlSiO 4) 6 · sodalite type compounds such 2MX. Here, MX represents a halide, X represents a halogen element, M represents Na, Sr, Ag, C
It means a metal element such as s and Ba. The solidification synthesis reaction is carried out by hydrothermal reaction of a compound containing a fission product halide. In order to accelerate the synthesis reaction, the mixture containing the halide is preferably compressed and solidified to be performed in the form of pellets.
【０００９】本発明では、水熱反応はオートクレーブの
ような耐圧密閉容器で温度８０〜３００℃、圧力０．１
〜５ＭＰａ、水の存在下で１〜６時間実施される。好ま
しい温度、圧力及び時間はそれぞれ１５０〜２５０℃、
０．１〜２ＭＰａ及び２〜６時間である。それぞれ温度
が８０℃未満及び時間が１時間未満の場合には、ソーダ
ライト型放射性廃棄物固化体に取込まれる核分裂生成物
のハロゲン化物の収率が低いため、好ましくない。また
温度が３００℃を超える場合、時間が６時間を超える場
合には、従来法との顕著な差異がなくなり、５ＭＰａを
超えても反応がそれ程促進されない。In the present invention, the hydrothermal reaction is carried out in a pressure-resistant closed vessel such as an autoclave at a temperature of 80 to 300 ° C. and a pressure of 0.1.
５5 MPa in the presence of water for 1 to 6 hours. Preferred temperatures, pressures and times are 150-250 ° C, respectively.
0.1 to 2 MPa and 2 to 6 hours. When the temperature is less than 80 ° C. and the time is less than 1 hour, the yield of the fission product halide taken into the solidified sodalite-type radioactive waste is not preferable. When the temperature exceeds 300 ° C. and when the time exceeds 6 hours, there is no significant difference from the conventional method, and the reaction does not accelerate so much even when it exceeds 5 MPa.
【００１０】[0010]
【実施例】次に本発明の実施例を説明する。 ＜実施例１＞ＮａＡｌＯ2、ＳｉＯ2及びＮａＩをモル比
で３：３：１の割合で十分に混合した。この混合物を乳
鉢で粉砕し、得られた粉末を３００ＭＰａ（３×１０8
Ｎ／ｍ2）の圧力で圧縮固化してペレットを作製した。
得られたペレットを１５０℃の温度に保ったオートクレ
ーブ内で圧力０．４ＭＰａで６時間水熱反応させること
により（ＮａＡｌＳｉＯ4）6・２ＮａＩの組成を有する
ソーダライト型ヨウ素廃棄物固化体を得た。Next, embodiments of the present invention will be described. The <Example 1> NaAlO 2, SiO 2 and NaI in a molar ratio of 3: 3 were mixed thoroughly in a ratio of 1. This mixture was crushed in a mortar and the resulting powder was crushed at 300 MPa (3 × 10 8
N / m 2 ) to obtain a pellet.
The resulting pellet was obtained sodalite type iodine wastes solidified body having a composition of (NaAlSiO 4) 6 · 2NaI by 6 hours hydrothermal reaction at a pressure 0.4MPa in an autoclave maintained at a temperature of 0.99 ° C. .
【００１１】＜実施例２＞ＮａＯＨ、カオリンを主体と
する材料（Ａｌ2Ｓｉ2Ｏ5（ＯＨ）4）及びＮａＩをモル
比で６：３：２の割合で十分に混合した。この混合物を
乳鉢で粉砕し、得られた粉末を３００ＭＰａの圧力で圧
縮固化してペレットを作製した。得られたペレットを１
５０℃の温度に保ったオートクレーブ内で圧力０．４Ｍ
Ｐａで６時間水熱反応させることにより（ＮａＡｌＳｉ
Ｏ4）6・２ＮａＩの組成を有するソーダライト型ヨウ素
廃棄物固化体を得た。Example 2 NaOH, a material mainly composed of kaolin (Al 2 Si 2 O 5 (OH) 4 ) and NaI were sufficiently mixed in a molar ratio of 6: 3: 2. This mixture was pulverized in a mortar, and the obtained powder was compressed and solidified at a pressure of 300 MPa to produce pellets. Pellets obtained are 1
0.4M pressure in an autoclave maintained at a temperature of 50 ° C
Hydrothermal reaction at Pa for 6 hours (NaAlSi
O 4) to give the sodalite type iodine wastes solidified body having a composition of 6 · 2NaI.
【００１２】＜実施例３＞Ａｇ2Ｏ、ＳｉＯ2、Ａｌ(Ｏ
Ｈ)3及びＡｇＩをモル比で３：６：６：２の割合で十分
に混合した。この混合物を乳鉢で粉砕し、得られた粉末
を３００ＭＰａの圧力で圧縮固化してペレットを作製し
た。得られたペレットを１５０℃の温度に保ったオート
クレーブ内で圧力０．４ＭＰａで６時間水熱反応させる
ことにより（ＡｇＡｌＳｉＯ4）6・２ＡｇＩの組成を有
するソーダライト型ヨウ素廃棄物固化体を得た。<Embodiment 3> Ag 2 O, SiO 2 , Al (O
H) 3 and AgI were mixed well in a molar ratio of 3: 6: 6: 2. This mixture was pulverized in a mortar, and the obtained powder was compressed and solidified at a pressure of 300 MPa to produce pellets. The resulting pellet was obtained sodalite type iodine wastes solidified body having a composition of (AgAlSiO 4) 6 · 2AgI by 6 hours hydrothermal reaction at a pressure 0.4MPa in an autoclave maintained at a temperature of 0.99 ° C. .
【００１３】＜実施例４＞Ａｇ2Ｏ、カオリンを主体と
する材料（Ａｌ2Ｓｉ2Ｏ5（ＯＨ）4）及びＡｇＩをモル
比で３：３：２の割合で十分に混合した。この混合物を
乳鉢で粉砕し、得られた粉末を３００ＭＰａの圧力で圧
縮固化してペレットを作製した。得られたペレットを１
５０℃の温度に保ったオートクレーブ内で圧力０．４Ｍ
Ｐａで６時間水熱反応させることにより（ＡｇＡｌＳｉ
Ｏ4）6・２ＡｇＩの組成を有するソーダライト型ヨウ素
廃棄物固化体を得た。Example 4 Ag 2 O, a material mainly composed of kaolin (Al 2 Si 2 O 5 (OH) 4 ), and AgI were sufficiently mixed in a molar ratio of 3: 3: 2. This mixture was pulverized in a mortar, and the obtained powder was compressed and solidified at a pressure of 300 MPa to produce pellets. Pellets obtained are 1
0.4M pressure in an autoclave maintained at a temperature of 50 ° C
Hydrothermal reaction at 6 Pa for 6 hours (AgAlSi
O 4) to give the sodalite type iodine wastes solidified body having a composition of 6 · 2AgI.
【００１４】＜評価＞本発明のソーダライト型放射性廃
棄物固化体の可能浸出性について、実施例１で得られた
ソーダライト型放射性廃棄物固化体についてのみ試験を
行った。その結果、ＡＮＳ（American National Standa
rd）方式によるＬＩ値（低レベル放射性廃棄物の可能浸
出値）で１２．８となり、モルタルセメント固化体の場
合（ＬＩ値７）よりも優れ、かつ従来の技術によるソー
ダライト固化体に関する報告値（ＬＩ値１２）と同等も
しくはそれ以上の優れた結果が得られた。<Evaluation> The possible leachability of the solidified sodalite-type radioactive waste of the present invention was tested only for the solidified sodalite-type radioactive waste obtained in Example 1. As a result, ANS (American National Standa
The LI value (possible leaching value of low-level radioactive waste) by the rd) method is 12.8, which is superior to that of the solidified mortar cement (LI value 7), and the reported value of the solidified sodalite by the conventional technology. Excellent results equivalent to or higher than (LI value 12) were obtained.
【００１５】[0015]
【発明の効果】以上述べたように、本発明のソーダライ
ト型放射性廃棄物固化体の合成方法によれば、ＮａＡｌ
Ｏ2、ＳｉＯ2、ＮａＯＨ、Ａｌ2Ｏ3、Ａｇ2Ｏ、Ａｌ(Ｏ
Ｈ)3及びカオリンを主体とする材料から選ばれた化合物
を適切に組合わせ、これに核分裂生成物のハロゲン化物
を混合し、温度８０〜３００℃、圧力０．１〜５ＭＰ
ａ、水の存在下で１〜６時間水熱反応させるので、従来
の合成方法に比べて、ヨウ素のようなハロゲン化物が揮
発して飛散するおそれがなく、高い収率でハロゲン化物
を取込んで固化するソーダライト型放射性廃棄物固化体
が得られる。合成温度が低くかつ合成時間が短くなるた
め、合成装置の負担が軽減され、しかもエネルギー消費
が少ないため、経済性に優れる効果がある。As described above, according to the method for synthesizing the solidified sodalite-type radioactive waste of the present invention, NaAl
O 2 , SiO 2 , NaOH, Al 2 O 3 , Ag 2 O, Al (O
H) A compound selected from a material mainly composed of 3 and kaolin, appropriately combined with a fission product halide, at a temperature of 80 to 300 ° C. and a pressure of 0.1 to 5 MPa.
a. Since the hydrothermal reaction is carried out in the presence of water for 1 to 6 hours, there is no possibility that the halide such as iodine is volatilized and scattered, and the halide is incorporated in a high yield as compared with the conventional synthesis method. A solidified sodalite-type radioactive waste is obtained. Since the synthesis temperature is low and the synthesis time is short, the load on the synthesis apparatus is reduced, and the energy consumption is small, so that there is an effect that the economy is excellent.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 加藤 博康 茨城県那珂郡那珂町大字向山字六人頭1002 番地の14 三菱マテリアル株式会社環境・ エネルギー研究所内 (72)発明者 中澤 俊之 茨城県那珂郡那珂町大字向山字六人頭1002 番地の14 三菱マテリアル株式会社環境・ エネルギー研究所内 (72)発明者 岡田 賢一 茨城県那珂郡那珂町大字向山字六人頭1002 番地の14 三菱マテリアル株式会社環境・ エネルギー研究所内 ────────────────────────────────────────────────── ─── Continuing on the front page (72) Inventor Hiroyasu Kato 1002, 6-headed head, Mukoyama, Naka-machi, Naka-gun, Naka-gun, Ibaraki Prefecture Mitsubishi Materials Environmental & Energy Research Laboratory (72) Inventor Toshiyuki Nakazawa Naka-gun, Ibaraki Mitsubishi Materials Corporation Environmental and Energy Research Institute (72) Inventor Kenichi Okada 1002 Mukaiyama, Rokujin-ji, 1002, 14-Mitsubishi Materials Corporation Energy Research Institute
Claims (8)
のハロゲン化物を混合し、温度１２０〜３００℃、圧力
０．１〜５ＭＰａ、水の存在下で１〜６時間水熱反応さ
せることによりソーダライト型放射性廃棄物固化体を得
ることを特徴とするソーダライト型放射性廃棄物固化体
の合成方法。1. Soda by mixing NaAlO 2 , SiO 2 and a halide of a fission product and subjecting them to a hydrothermal reaction at a temperature of 120 to 300 ° C. under a pressure of 0.1 to 5 MPa for 1 to 6 hours in the presence of water. A method for synthesizing a solid sodalite-type radioactive waste, comprising obtaining a solidified radioactive-type waste.
裂生成物のハロゲン化物を混合し、温度１２０〜３００
℃、圧力０．１〜５ＭＰａ、水の存在下で１〜６時間水
熱反応させることによりソーダライト型放射性廃棄物固
化体を得ることを特徴とするソーダライト型放射性廃棄
物固化体の合成方法。2. Mixing NaOH, Al 2 O 3 , SiO 2 and a fission product halide at a temperature of 120-300.
C., a pressure of 0.1 to 5 MPa, and a hydrothermal reaction in the presence of water for 1 to 6 hours to obtain a solidified sodalite-type radioactive waste, which is characterized by obtaining a solidified sodalite-type radioactive waste. .
び核分裂生成物のハロゲン化物を混合し、温度８０〜３
００℃、圧力０．１〜５ＭＰａ、水の存在下で１〜６時
間水熱反応させることによりソーダライト型放射性廃棄
物固化体を得ることを特徴とするソーダライト型放射性
廃棄物固化体の合成方法。3. A material mainly composed of NaOH and kaolin and a fission product halide are mixed at a temperature of 80-3.
Synthesis of solidified sodalite-type radioactive waste, characterized in that solidified sodalite-type radioactive waste is obtained by performing a hydrothermal reaction at 00 ° C. under a pressure of 0.1 to 5 MPa in the presence of water for 1 to 6 hours. Method.
分裂生成物のハロゲン化物を混合し、温度１２０〜３０
０℃、圧力０．１〜５ＭＰａ、水の存在下で１〜６時間
水熱反応させることによりソーダライト型放射性廃棄物
固化体を得ることを特徴とするソーダライト型放射性廃
棄物固化体の合成方法。4. Mixing Ag 2 O, SiO 2 , Al (OH) 3 and a fission product halide at a temperature of 120-30.
Synthesis of solidified sodalite-type radioactive waste characterized by obtaining a solidified sodalite-type radioactive waste by performing a hydrothermal reaction at 0 ° C. under a pressure of 0.1 to 5 MPa in the presence of water for 1 to 6 hours. Method.
（ＯＨ）3び核分裂生成物のハロゲン化物を混合し、温
度１２０〜３００℃、圧力０．１〜５ＭＰａ、水の存在
下で１〜６時間水熱反応させることによりソーダライト
型放射性廃棄物固化体を得ることを特徴とするソーダラ
イト型放射性廃棄物固化体の合成方法。5. Ag 2 O, NaAlO 2 , SiO 2 , Al
(OH) 3 A fission product halide is mixed and subjected to a hydrothermal reaction at a temperature of 120 to 300 ° C., a pressure of 0.1 to 5 MPa, and in the presence of water for 1 to 6 hours to solidify sodalite-type radioactive waste. A method for synthesizing a solidified sodalite-type radioactive waste, comprising obtaining a solid.
び核分裂生成物のハロゲン化物を混合し、温度８０〜３
００℃、圧力０．１〜５ＭＰａ、水の存在下で１〜６時
間水熱反応させることによりソーダライト型放射性廃棄
物固化体を得ることを特徴とするソーダライト型放射性
廃棄物固化体の合成方法。6. A mixture of Ag 2 O, a material mainly composed of kaolin, and a halide of fission products, and the mixture is mixed at a temperature of 80-3.
Synthesis of solidified sodalite-type radioactive waste, characterized in that solidified sodalite-type radioactive waste is obtained by performing a hydrothermal reaction at 00 ° C. under a pressure of 0.1 to 5 MPa in the presence of water for 1 to 6 hours. Method.
化物がＮａＸ、ＡｇＸ又はＸ2である請求項１ないし６
いずれか記載の合成方法。7. When the halogen element is X, the halide is NaX, AgX or X 2.
The synthesis method according to any of the above.
載の合成方法。8. The method according to claim 7, wherein the halogen element is iodine.
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|---|---|---|---|
| JP11156506A JP2000346994A (en) | 1999-06-03 | 1999-06-03 | Synthesizing method of sodalite type radioactive waste solidified body |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11156506A JP2000346994A (en) | 1999-06-03 | 1999-06-03 | Synthesizing method of sodalite type radioactive waste solidified body |
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| Publication Number | Publication Date |
|---|---|
| JP2000346994A true JP2000346994A (en) | 2000-12-15 |
Family
ID=15629262
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| JP11156506A Withdrawn JP2000346994A (en) | 1999-06-03 | 1999-06-03 | Synthesizing method of sodalite type radioactive waste solidified body |
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| Country | Link |
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| JP (1) | JP2000346994A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2014013236A (en) * | 2012-06-29 | 2014-01-23 | Ge-Hitachi Nuclear Energy Americas Llc | System and method for processing and storing cooling liquid after accident |
| CN111863305A (en) * | 2020-08-20 | 2020-10-30 | 中国原子能科学研究院 | Method for curing radioactive iodine-containing silver-coated silica gel |
| CN114678154A (en) * | 2022-03-25 | 2022-06-28 | 西南科技大学 | Low-temperature curing method of waste silica gel containing radioactive iodine |
-
1999
- 1999-06-03 JP JP11156506A patent/JP2000346994A/en not_active Withdrawn
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2014013236A (en) * | 2012-06-29 | 2014-01-23 | Ge-Hitachi Nuclear Energy Americas Llc | System and method for processing and storing cooling liquid after accident |
| US9368241B2 (en) | 2012-06-29 | 2016-06-14 | Ge-Hitachi Nuclear Energy Americas Llc | System and method for processing and storing post-accident coolant |
| CN111863305A (en) * | 2020-08-20 | 2020-10-30 | 中国原子能科学研究院 | Method for curing radioactive iodine-containing silver-coated silica gel |
| CN114678154A (en) * | 2022-03-25 | 2022-06-28 | 西南科技大学 | Low-temperature curing method of waste silica gel containing radioactive iodine |
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