JPS6025498A - Glass solidifying treating method of radioactive waste - Google Patents
Glass solidifying treating method of radioactive wasteInfo
- Publication number
- JPS6025498A JPS6025498A JP13397583A JP13397583A JPS6025498A JP S6025498 A JPS6025498 A JP S6025498A JP 13397583 A JP13397583 A JP 13397583A JP 13397583 A JP13397583 A JP 13397583A JP S6025498 A JPS6025498 A JP S6025498A
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- lime
- glass
- treating method
- clay
- 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)
- Fertilizers (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】
本発明は放射性廃棄物の１５ラス固化処理方法に関する
。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a 15 lath solidification treatment method for radioactive waste.
近年、放射性廃棄物の減容化処理を促進する方法として
、放射性廃棄物をガラス同化体の内部に取り込まぜる方
法が開発された。この方法は、原子力発ｒ１．Ｈ所（Ｒ
ＷＲ）から発生する濃縮廃液（２０％程度のＮａ２ＳＯ
４を含む）の乾燥固型分と、５ｉ０２を主成分とする粘
土等を混合し、これを約１．２００℃の高温で溶融する
ことにより以下のようなガラス化反応を起こさせ、その
後冷却固化するというものである。In recent years, a method of incorporating radioactive waste into a glass assimilate has been developed as a method for promoting the volume reduction treatment of radioactive waste. This method uses nuclear power r1. H place (R
Concentrated waste liquid (approximately 20% Na2SO) generated from
4) and clay, etc. whose main component is 5i02, are melted at a high temperature of about 1.200°C to cause the following vitrification reaction, and then cooled. It solidifies.
１′
Ｎａ２ＳＯ４＋ｎＳ １０２−＋Ｎａ２０−ｎＳ ｉ０
２ ＋ＳＯ２↑＋７０２↑ところで上記ハラス化反応中
、Ｎａ ２Ｏ−ｎＳ ｉ ０２はソータシリカカラスで
あるが、使用する粘土がアル三す等の安定酸化物をほと
んど含まない場合、ソータシリカカラスのアルカリ成分
は水に溶は易も）という性質を有する。したがって、将
来陸地処分もしくは海洋処分される放射性廃棄物同化体
に使用するとその中に含まれる放射性物質が出水やｄＩ
ｆ水に溶は出し汚染が広がる危険性がある。1' Na2SO4+nS 102-+Na20-nS i0
2 +SO2↑+702↑By the way, during the above halasing reaction, Na2O-nS i 02 is sorta silica glass, but if the clay used contains almost no stable oxides such as aluminum, the alkaline component of sorta silica glass It has the property of being easily soluble in water. Therefore, if it is used in assimilated radioactive waste that will be disposed of on land or in the ocean in the future, the radioactive materials contained therein may be released into water or dI.
f There is a risk that it will dissolve into water and spread contamination.
本発明はこのような問題を解決することを［Ｉ ｒｌ’
Ｊとし、原子力発電所等から発生する放射性１３６葉物
の乾燥固型分と粘土等の５ｉ０２を主成分とする助剤の
混合物を高温で溶融し固化する際に、混合物用量に対し
て１０〜３０％の石灰を添加することを特徴とする放射
性廃棄物のガラス同化処理方法を提供することによって
、その目的を達成するものであり、これにより、耐水溶
性に優れｔこ安定した月ラス固化体を得ることができ、
もって処分１１４周辺を放射性物質で汚染させなくて済
むものである。The present invention aims to solve such problems [I rl'
J, when melting and solidifying a mixture of dry solid content of radioactive 136 leaves generated from nuclear power plants etc. and an auxiliary agent mainly composed of 5i02 such as clay at a high temperature, 10 to 10% of the amount of the mixture is This purpose is achieved by providing a glass assimilation treatment method for radioactive waste characterized by the addition of 30% lime, which results in a stable glass solidified material with excellent water solubility. you can get
This eliminates the need to contaminate the area around the disposal site 114 with radioactive materials.
以下本発明の方法を、その一実施例を示す図面にＪ、１
；づいて詳細に説明す゛る。The method of the present invention is illustrated in the drawings J and 1 showing one embodiment thereof.
; Next, I will explain in detail.
第１図に示すように、先ず原子力発電所（１）から発生
した放射性０縮廃液（２）を乾燥固形化（３）する。As shown in FIG. 1, first, the radioactive waste liquid (2) generated from the nuclear power plant (1) is dried and solidified (3).
これにより乾燥塩（乾燥固型分）（４）が得られる。This yields dry salt (dry solids) (4).
一方、助剤として粘土（５）を準備するとともにｓ １
５ラス形成安定剤として石灰（６）を準備する。なお、
枯−１＝ （！’ｉ）の主成分は５ｉ０２である。Meanwhile, while preparing clay (5) as an auxiliary agent, s 1
5. Prepare lime (6) as lath formation stabilizer. In addition,
The main component of dry-1= (!'i) is 5i02.
次に、乾燥塩（４）と粘土（５）を混合（７）する。こ
のとき乾燥塩（４）の量が少なすぎると混合物は溶融し
ても充分な１５ラス化反応を起こすことができず、また
、乾燥塩（４）の量が多すぎても未反応の乾燥塩が残り
不・１；舊である。したがって、乾燥塩（４）の割合は
・ｌ’／Ｉ燥ｊ１．に（４）と粘土（５）の混合物全体
の３０へ一５０重量％が’＋ｌ’、”：ｌ 、Ｑｌでよ
、る。そしてこの合計重量（混合物Ｊ１′を鼠）にマ、
［シて１０〜３０％の石灰（６）を添加し混合（７）す
る。Next, the dry salt (4) and clay (5) are mixed (7). At this time, if the amount of drying salt (4) is too small, the mixture will not be able to cause a sufficient 15 lath reaction even if it is melted, and if the amount of drying salt (4) is too large, unreacted dry There is no salt left. Therefore, the ratio of dry salt (4) is l'/I dry j1. 30 to 50% by weight of the entire mixture of (4) and clay (5) is expressed as '+l', ”:l, Ql.And this total weight (mixture J1' is a mouse) is
[Add 10-30% lime (6) and mix (7).
次に、これら乾燥塩（４）と、粘土（！ｉ）と、石灰（
６）の１、ｉＡ合物をｌ？ｊ融炉において加熱溶融＋８
） Ｌ ｈ容器に流し込／してフ）うス固化（９）する
。これによりｊ５うス固化体を形成する。そして、適宜
陸ｆ１１や海洋に処分αＯする。Next, these dry salt (4), clay (!i), and lime (
6) 1, iA compound as l? j Heating and melting in a melting furnace +8
) Pour into Lh container and solidify the film (9). This forms a j5 thin solidified body. Then, it is disposed of on land f11 or in the ocean αO as appropriate.
このような方法において、乾燥塩（４）を４０重Ｌ１％
、粘土（５）を６０重量％の割合とし、この合羽ＬＲ量
に対して５〜５０％の石灰（６）を添加混合（７）シて
試料を作成した。かかる混合物を８０ｙ定眼しるつぼに
取り１２００℃で１時四電９気炉にて溶融（８）シ、得
られた乃ラス固化体についてＪＩＳ−Ｒ８５０２に規定
されｔこ方法でアルカリ溶出試験を行った。In such a method, dry salt (4) is added at 40 weight L1%.
A sample was prepared by adding and mixing (7) clay (5) in a proportion of 60% by weight and lime (6) in an amount of 5 to 50% with respect to the amount of Kappa LR. The mixture was placed in an 80mm crucible and melted in a 9-air furnace at 1200°C for 1 hour (8), and the resulting solidified material was subjected to an alkali elution test using the method specified in JIS-R8502. went.
第２図はこのアルカリ溶出試験で明らかとなった石灰（
６）の添加量とアルカリ溶出率のじ４係を示す。Figure 2 shows the lime (
6) shows the relationship between the amount added and the alkali elution rate.
すなわち、石灰（６）の添加量が８０爪星％を越える場
合およびｌＯ重重量に満たない場合は１２００”Ｃ，１
時間という実験条件では充分良質なｔｊガラスならず不
適であったが、これと反対に、石灰（６）の添加量が１
０〜３０重量％の範囲内である場合はアルカリ溶出率が
大１」に減少し、耐水溶性にイ・ヴれだ安定しｔコカラ
ス固化体が得られた。In other words, if the amount of lime (6) added exceeds 80% or less than 10% by weight, 1200"C, 1
Under the experimental conditions of time, TJ glass was not of sufficient quality and was not suitable, but on the contrary, when the amount of lime (6) added was 1
When the content was within the range of 0 to 30% by weight, the alkali elution rate decreased to about 1", and a solidified product with stable water solubility was obtained.
以上本発明の方法に≠れば、耐水１溶性に優れた安定し
たガラス同化体を得ることができる。しｔこがりＣ１処
分地周辺を放射性物質で汚染させなくて済む。By using the method of the present invention as described above, a stable glass assimilate having excellent water resistance and solubility can be obtained. There is no need to contaminate the area around the C1 disposal site with radioactive materials.
７１ 図！（■１の筒中、な説明
図面は本発明方法を説明するためのもので、第１１／Ｉ
は）［１−図、第２図は石灰添加用とハうス固化体のア
ルカリ溶出率の関係をあられず［￥Ｊである、。71 Figure! (The explanatory drawing in the cylinder of ■1 is for explaining the method of the present invention, and is
) [Figure 1 and Figure 2 show the relationship between lime addition and the alkali elution rate of the house solidified body [¥J].
１１）・・・原子力発ｎ【所、（２）・・・放射性門稲
廃液、（３）・・・’：’／、 ’ｌｉ’７ｊ 固型化
、（４）・・・乾燥塩、（５）−粘土、ｆ６） −石灰
、（７）混合、（８）・・加熱溶融、（９）・・・１３
ラス固化代１］ｒ！大 森 木 義 弘
第を図
１
第７図
石Ｆｆ！添〃ｕ量（りＹガヒリｈイー粘土に対手ケ更が
ン（％）11)...Nuclear power plant, (2)...Radioactive waste liquid, (3)...':'/, 'li'7j solidification, (4)...Dry salt, (5) - Clay, f6) - Lime, (7) Mixing, (8) Heat melting, (9)...13
Lath solidification amount 1] r! Figure 1 Figure 7 Stone Ff! Amount of addition (%)
Claims (1)
型分と粘土等のＳｉＯ□を主成分とする助剤の混合物を
高温で溶融し固化する際に、混合物重量に対して１０〜
３０％の石灰を添加することを持ｆ：☆とする放射性廃
棄物のガラス同化処理力？夫。1. When melting and solidifying a mixture of dry solid radioactive waste generated from nuclear power plants, etc. and an auxiliary agent such as clay whose main component is SiO
What is the assimilation power of radioactive waste glass by adding 30% lime? husband.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP13397583A JPS6025498A (en) | 1983-07-21 | 1983-07-21 | Glass solidifying treating method of radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP13397583A JPS6025498A (en) | 1983-07-21 | 1983-07-21 | Glass solidifying treating method of radioactive waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6025498A true JPS6025498A (en) | 1985-02-08 |
Family
ID=15117446
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP13397583A Pending JPS6025498A (en) | 1983-07-21 | 1983-07-21 | Glass solidifying treating method of radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6025498A (en) |
-
1983
- 1983-07-21 JP JP13397583A patent/JPS6025498A/en active Pending
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