JPS60142297A - Method of treating radioactive waste - Google Patents
Method of treating radioactive wasteInfo
- Publication number
- JPS60142297A JPS60142297A JP25151583A JP25151583A JPS60142297A JP S60142297 A JPS60142297 A JP S60142297A JP 25151583 A JP25151583 A JP 25151583A JP 25151583 A JP25151583 A JP 25151583A JP S60142297 A JPS60142297 A JP S60142297A
- Authority
- JP
- Japan
- Prior art keywords
- basicity
- radioactive waste
- cao
- waste
- furnace
- 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)
- Treatment Of Sludge (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】
本発明は例えば原子力発電施設等から排出される放射能
に汚染された廃棄物の処理方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for treating radioactively contaminated waste discharged from, for example, nuclear power generation facilities.
上記廃棄物の多くは無機固形物であシーたん溶融した後
固化するいわゆる溶融処理は外界に対する放射能二次汚
染の防止手段として有力なものである。しかし該溶融処
理によって得られた固化物は破砕され易いものあるいは
崩壊し易いものであれば、その破砕物、崩壊物が外界に
飛散して二次汚染の原因となるおそれが多分にある。Most of the above-mentioned wastes are inorganic solids, and so-called melting treatment, in which they are immediately melted and then solidified, is an effective means of preventing secondary radioactive contamination to the outside world. However, if the solidified product obtained by the melting process is easily crushed or disintegrated, there is a high possibility that the crushed or disintegrated products will be scattered into the outside world and cause secondary pollution.
本発明は上記従来の問題点を解決するここを目的とし、
廃棄物の塩基度(CaO/5iO2)を調節することを
骨子とする。The present invention aims to solve the above-mentioned conventional problems,
The main point is to adjust the basicity (CaO/5iO2) of the waste.
本発明を以下に詳細に説明する。The invention will be explained in detail below.
本発明の対象とする廃棄物としては原子力発電施設の場
合には第1表のようなものがある。In the case of nuclear power generation facilities, the waste to be covered by the present invention is as shown in Table 1.
第1表
上記廃棄物は例えばアーク炉、直接通電式溶融炉、燃焼
式溶融炉、マイクロ波溶融炉等の内部で直接、もしくは
内部に溶融されている溶融金属上に投入することにより
溶融され、その後炉から取出されて冷却固化される。か
くして得られる固形物の物性は該固化物中に含まれるC
aOと5i02との比(CaO/5i02 :塩基度と
云う)によって以下のように変化する。Table 1 The above wastes are melted, for example, directly inside an arc furnace, direct current melting furnace, combustion type melting furnace, microwave melting furnace, etc., or by being poured onto molten metal melted therein. It is then taken out of the furnace and cooled and solidified. The physical properties of the solid obtained in this way are determined by the C contained in the solid.
It changes as follows depending on the ratio of aO and 5i02 (CaO/5i02: basicity).
第2表によれば塩基度が0.5以下ではガラス質になり
破砕し易く、0.5〜1.0では溶融物の冷却時100
0°C前後においてゆるやかに徐冷する熱処理によって
結晶成長が起るようになり、硬く破砕しにくい固化物が
得られ、1.0〜2.5では溶融物の自然放冷で結晶成
長が起り、硬く破砕[2にくい固化物が得られ、2.0
以上特に2.5以上では水を吸収して崩壊する傾向が次
第に大きくなる。したがって固化物の塩基度を0.5〜
2.5、望址しくは1.0〜2.0の範囲に調節すれば
長期にわたって破砕も崩壊もしない。したがって二次汚
染の危険のない岩石状の固化物が得られる。According to Table 2, when the basicity is less than 0.5, it becomes glassy and easily fractures, and when the basicity is from 0.5 to 1.0, the melt becomes 100%
Crystal growth occurs through heat treatment of slow cooling at around 0°C, resulting in a solidified material that is hard and difficult to crush, and at temperatures between 1.0 and 2.5, crystal growth occurs due to natural cooling of the molten material. , hard crushing [2 hard solidified material was obtained, 2.0
In particular, when the number is 2.5 or more, the tendency to absorb water and disintegrate gradually increases. Therefore, the basicity of the solidified product should be 0.5~
If adjusted to a value of 2.5, preferably in the range of 1.0 to 2.0, it will not shatter or disintegrate over a long period of time. Therefore, a rock-like solidified product can be obtained without the risk of secondary contamination.
第1表によれば廃棄物のすべての種類のものが塩基度0
,5〜2.5、望ましくは1.0〜2.0の範囲のもの
であるとは限ら々い。そこで本発明においては廃棄物の
CaOおよびSiO直有量をめ、該含有証から塩基度を
算出し、該塩基度が0.5〜2.5、望ましくは1.0
〜2.0になるようにCaOおよび/またはSiq成分
を添加するのである。CaOおよび5iOJ有量は第1
表記載の廃棄物であればそれらの混合割合および処理量
から大体の値を分析することなく第1表を利用して算出
することが出来る。According to Table 1, all types of waste have a basicity of 0.
, 5 to 2.5, preferably 1.0 to 2.0. Therefore, in the present invention, the basicity is calculated from the content evidence based on the direct amount of CaO and SiO in the waste, and the basicity is 0.5 to 2.5, preferably 1.0.
CaO and/or Siq components are added so that the value becomes ~2.0. CaO and 5iOJ abundance is the first
If the waste is listed in the table, approximate values can be calculated using Table 1 from the mixing ratio and processing amount without analysis.
またCaOおよび/−1:たは5iOz成分としては(
:’aO+5i02月う体でなく第1表に明らかなよう
にCaO成分としてはCaOリンチな、即ち塩基度の大
きなコンクリート等のCaO複合物、5i02成分とし
ては5i02リツチな、即ち塩基度の小さな保温材、ガ
ラス等のSiO□複合物が用いられ得る。In addition, CaO and /-1: or 5iOz components (
:'aO+5i02 As is clear from Table 1, rather than a CaO compound, the CaO component is CaO rich, that is, a CaO composite such as concrete with a high basicity, and the 5i02 component is a 5i02 rich, that is, a heat insulating material with a small basicity. SiO□ composites such as materials, glasses, etc. can be used.
第1図には本発明に用いられる直接通電式溶融炉が示さ
れる。図において、直接通電式溶融炉(1)は耐火物か
らなる炉体(2)と、該炉体(2)の中間に挟着される
水冷壁(3)と、該炉体(2)の両側から挿入される主
電極(4) 、 (5)と、上面に設けられた投入口(
6)と、上面に被着され点検CI (71)と排気管(
72)とを有する炉蓋(7)と、側面に開口する溶融物
取出し口(8)と、該取出し1垣8)直下に配されて溶
融物を受取る樋体(9)とからなシ、炉(1)は架台θ
0」二に搭載されている。廃棄物は塩基度を所定の値に
調節された後投入コンベア(ロ)を介して投入口(6)
から炉(1)内に投入される。投入口(6)はシリンダ
(61)によって開閉される。炉(1)内には予め金属
が溶融されており、廃棄物(13は該金属溶融層θり上
に投入され溶融される。廃棄物aつはかくして溶融して
取出し口(8)から取出され冷却固化されつ\樋体(9
)を介して固化物は受け器α荀に蓄積される。FIG. 1 shows a direct current type melting furnace used in the present invention. In the figure, a direct current melting furnace (1) has a furnace body (2) made of refractory, a water-cooled wall (3) sandwiched between the furnace body (2), and a furnace body (2). The main electrodes (4) and (5) are inserted from both sides, and the input port (
6), the inspection CI (71) and the exhaust pipe (
A furnace lid (7) having a furnace cover (72), a melt outlet (8) opening on the side, and a gutter body (9) disposed directly below the outlet (8) to receive the melt, Furnace (1) is mounted on mount θ
0” is installed on the second. After the basicity of the waste has been adjusted to a predetermined value, the waste is transferred to the input port (6) via the input conveyor (b).
It is then put into the furnace (1). The input port (6) is opened and closed by a cylinder (61). The metal is melted in advance in the furnace (1), and the waste (13) is thrown onto the molten metal layer θ and melted.The waste a is thus melted and taken out from the outlet (8). The gutter body (9) is cooled and solidified.
), the solidified material is accumulated in the receiver αxun.
本発明は上記実施例によって限定されるものではなく、
炉は直接通電式溶融炉以外に燃焼式溶融炉、アーク炉、
マイクロ波溶融炉等が用いられ得るし、金属溶融物を用
いず廃棄物を直接加熱して溶融してもよい。かくして得
られた本発明の固化物は岩石状で破砕、崩壊しにく\コ
ンクI7)骨材等の再利用に安全に供することが出来る
。The present invention is not limited to the above examples,
Furnaces include combustion type melting furnaces, arc furnaces, and direct current type melting furnaces.
A microwave melting furnace or the like may be used, or the waste may be directly heated and melted without using a metal melt. The solidified product of the present invention thus obtained is rock-like and difficult to crush and disintegrate.\Conc I7) It can be safely reused as aggregate, etc.
第1図は本発明に用いられる装置の一部切欠き斜視図で
ある。
図中 (1)・・・炉、(6)・・金属溶融層、ol・
・・廃棄物、特許出願人 大同特殊鋼株式会社FIG. 1 is a partially cutaway perspective view of the apparatus used in the present invention. In the figure (1)...furnace, (6)...metal molten layer, ol...
...Waste, patent applicant Daido Steel Co., Ltd.
Claims (1)
の塩基度(CaO/5i02)を測定し、該測定値にも
とづいて所定量のCaOおよび/または5i02を添加
し、所定の塩基度に調節することを特徴とする放射性廃
棄物の処理方法(2)該所定の塩基度(CaO/5i0
2 )は0.7〜2.5の範囲である[特許請求の範囲
(1月に記載の放射性廃棄物の処理方法 (3)該放射性廃棄物は放射性物質に汚染された焼却灰
、保温材、濾材、コンクリートである]特許請求の範囲
(1)および(2月に記載の放射性廃棄物の処理方法[Claims] (1) When melting radioactive waste, the basicity (CaO/5i02) of the waste is measured, and a predetermined amount of CaO and/or 5i02 is added based on the measured value. , a method for treating radioactive waste characterized by adjusting the basicity to a predetermined basicity (2) The predetermined basicity (CaO/5i0
2) is in the range of 0.7 to 2.5 [Claims (method for disposing of radioactive waste described in January (3)) The radioactive waste is incinerated ash contaminated with radioactive materials, heat insulating material , a filter medium, and concrete] Claim (1) and (a method for disposing of radioactive waste described in February)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP25151583A JPS60142297A (en) | 1983-12-28 | 1983-12-28 | Method of treating radioactive waste |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP25151583A JPS60142297A (en) | 1983-12-28 | 1983-12-28 | Method of treating radioactive waste |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS60142297A true JPS60142297A (en) | 1985-07-27 |
Family
ID=17223958
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP25151583A Pending JPS60142297A (en) | 1983-12-28 | 1983-12-28 | Method of treating radioactive waste |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS60142297A (en) |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0556409A4 (en) * | 1991-09-06 | 1994-01-12 | Kabushiki Kaisha Kobe Seiko Sho | |
JP2013076690A (en) * | 2011-09-13 | 2013-04-25 | Taiheiyo Cement Corp | Method for removing radioactive cesium and method for manufacturing burned product |
JP2014106017A (en) * | 2012-11-26 | 2014-06-09 | Taiheiyo Cement Corp | Removing method of radioactive cesium and calcined object manufacturing method |
JP2014130051A (en) * | 2012-12-28 | 2014-07-10 | Taiheiyo Cement Corp | Method for removing radioactive cesium and method for manufacturing burned product |
JP2016148669A (en) * | 2016-03-01 | 2016-08-18 | 日本碍子株式会社 | Treatment method of radioactive cesium contaminant |
JP2016191716A (en) * | 2012-10-29 | 2016-11-10 | 太平洋セメント株式会社 | Radioactive cesium removal method and burned product manufacturing method |
-
1983
- 1983-12-28 JP JP25151583A patent/JPS60142297A/en active Pending
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0556409A4 (en) * | 1991-09-06 | 1994-01-12 | Kabushiki Kaisha Kobe Seiko Sho | |
JP2013076690A (en) * | 2011-09-13 | 2013-04-25 | Taiheiyo Cement Corp | Method for removing radioactive cesium and method for manufacturing burned product |
JP2016191716A (en) * | 2012-10-29 | 2016-11-10 | 太平洋セメント株式会社 | Radioactive cesium removal method and burned product manufacturing method |
JP2014106017A (en) * | 2012-11-26 | 2014-06-09 | Taiheiyo Cement Corp | Removing method of radioactive cesium and calcined object manufacturing method |
JP2014130051A (en) * | 2012-12-28 | 2014-07-10 | Taiheiyo Cement Corp | Method for removing radioactive cesium and method for manufacturing burned product |
JP2016148669A (en) * | 2016-03-01 | 2016-08-18 | 日本碍子株式会社 | Treatment method of radioactive cesium contaminant |
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