JPS6236594A - Melting solidifying processing method of radioactive waste - Google Patents
Melting solidifying processing method of radioactive wasteInfo
- Publication number
- JPS6236594A JPS6236594A JP60176109A JP17610985A JPS6236594A JP S6236594 A JPS6236594 A JP S6236594A JP 60176109 A JP60176109 A JP 60176109A JP 17610985 A JP17610985 A JP 17610985A JP S6236594 A JPS6236594 A JP S6236594A
- Authority
- JP
- Japan
- Prior art keywords
- metal
- radioactive waste
- melting point
- low melting
- metal compound
- 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.)
- Granted
Links
- 238000002844 melting Methods 0.000 title claims description 32
- 230000008018 melting Effects 0.000 title claims description 30
- 239000002901 radioactive waste Substances 0.000 title claims description 19
- 238000003672 processing method Methods 0.000 title 1
- 229910052751 metal Inorganic materials 0.000 claims description 25
- 239000002184 metal Substances 0.000 claims description 25
- 230000000694 effects Effects 0.000 claims description 20
- 150000002736 metal compounds Chemical class 0.000 claims description 18
- 238000000034 method Methods 0.000 claims description 14
- 230000005855 radiation Effects 0.000 claims description 12
- 229910000464 lead oxide Inorganic materials 0.000 claims description 9
- YEXPOXQUZXUXJW-UHFFFAOYSA-N oxolead Chemical compound [Pb]=O YEXPOXQUZXUXJW-UHFFFAOYSA-N 0.000 claims description 9
- 229910000410 antimony oxide Inorganic materials 0.000 claims description 4
- 238000010438 heat treatment Methods 0.000 claims description 4
- VTRUBDSFZJNXHI-UHFFFAOYSA-N oxoantimony Chemical compound [Sb]=O VTRUBDSFZJNXHI-UHFFFAOYSA-N 0.000 claims description 4
- 229910000416 bismuth oxide Inorganic materials 0.000 claims description 3
- TYIXMATWDRGMPF-UHFFFAOYSA-N dibismuth;oxygen(2-) Chemical compound [O-2].[O-2].[O-2].[Bi+3].[Bi+3] TYIXMATWDRGMPF-UHFFFAOYSA-N 0.000 claims description 3
- 239000008187 granular material Substances 0.000 claims description 3
- WABPQHHGFIMREM-UHFFFAOYSA-N lead(0) Chemical compound [Pb] WABPQHHGFIMREM-UHFFFAOYSA-N 0.000 claims description 3
- 239000000843 powder Substances 0.000 claims description 3
- 238000001816 cooling Methods 0.000 claims description 2
- 239000000126 substance Substances 0.000 description 9
- 238000007711 solidification Methods 0.000 description 8
- 230000008023 solidification Effects 0.000 description 7
- 239000000463 material Substances 0.000 description 5
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 description 4
- 239000004568 cement Substances 0.000 description 4
- 239000000919 ceramic Substances 0.000 description 4
- 239000003795 chemical substances by application Substances 0.000 description 4
- 229910001220 stainless steel Inorganic materials 0.000 description 4
- 239000010935 stainless steel Substances 0.000 description 4
- 238000004017 vitrification Methods 0.000 description 4
- 239000010426 asphalt Substances 0.000 description 3
- 229940125961 compound 24 Drugs 0.000 description 3
- 238000007496 glass forming Methods 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 150000002739 metals Chemical class 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- 239000004033 plastic Substances 0.000 description 3
- 239000002699 waste material Substances 0.000 description 3
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 2
- 229910000029 sodium carbonate Inorganic materials 0.000 description 2
- 239000004067 bulking agent Substances 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000001747 exhibiting effect Effects 0.000 description 1
- 239000000945 filler Substances 0.000 description 1
- 230000009970 fire resistant effect Effects 0.000 description 1
- 239000011521 glass Substances 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 239000010857 liquid radioactive waste Substances 0.000 description 1
- 230000010355 oscillation Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 239000002900 solid radioactive waste Substances 0.000 description 1
Landscapes
- 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】
［産業上の利用分野］
本発明は、マイクロ波加熱により酸化鉛や酸化アンチモ
ンのような放射線遮蔽効果もしくは減衰効果のある低融
点の金属もしくは金属化合物で放射性廃棄物を固化処理
する方法に関する。[Detailed Description of the Invention] [Industrial Application Field] The present invention is directed to the treatment of radioactive waste with a metal or metal compound with a low melting point that has a radiation shielding or attenuating effect, such as lead oxide or antimony oxide, by microwave heating. Concerning a method of solidification treatment.
［従来の技術］
原子炉や再処理施設、あるいは核燃料施設等からは放射
性物質を含む廃棄物が発生する。このような放射性廃棄
物は、更に安全な保管や安全な廃棄処分を行うために固
化処理される。[Prior Art] Waste containing radioactive materials is generated from nuclear reactors, reprocessing facilities, nuclear fuel facilities, and the like. Such radioactive waste is solidified for safer storage and safe disposal.
放射性廃棄物の固化処理方法としては、セメント、アス
ファルト、プラスチック、ガラス等を用いた固化法が行
われている。Solidification methods using cement, asphalt, plastic, glass, etc. are used to solidify radioactive waste.
［発明が解決しようとする問題点］
セメント固化法は常温で固化できるため装置が簡単で操
作も容易であり、比較的安価に行なえる利点がある反面
、セメントや砂などが増量剤となるため容積や重量が極
めて大きくなり、輸送や最終貯蔵する場合のスペースや
費用が大きくなる欠点がある。[Problems to be solved by the invention] The cement solidification method can solidify at room temperature, so the equipment is simple and easy to operate, and it has the advantage of being relatively inexpensive, but on the other hand, cement and sand are used as bulking agents. This has the disadvantage that the volume and weight are extremely large, requiring a large amount of space and cost for transportation and final storage.
アスファルト固化法やプラスチック固化法は比較的低い
温度で作業できる利点があるが、セメント固化法はどで
はないにしてもアスファルトやプラスチックが増量剤と
なるし、放射線に対する減衰効果がほとんどなく、また
火災に弱いという大きな欠点がある。The asphalt solidification method and the plastic solidification method have the advantage of being able to work at relatively low temperatures, but the cement solidification method uses asphalt and plastic as fillers, has little effect attenuating radiation, and is fire resistant. The major drawback is that it is weak.
更にガラス固化法はガラス化のためにかなり高い温度が
必要であるし、また放射線に対する遮蔽効果が少ない欠
点がある。その他、高レベル廃液のガラス固化に必要な
ガラス成形剤添加量の割合が大きい欠点もある０例えば
典型的な比率としては、放射性廃液３０重量％に対して
ガラス成形剤７０重量％程度ある。ガラス成形剤は熱伝
達効率が悪いから、その割合がこれより少なくなると実
用規模の固化体では崩壊熱の除去が困難となり、温度上
昇が著しくなってしまうからである。Furthermore, the vitrification method requires a considerably high temperature for vitrification, and also has the disadvantage that it has little radiation shielding effect. Another drawback is that the proportion of glass forming agent added necessary for vitrification of high-level waste liquid is large. For example, a typical ratio is about 70% by weight of glass forming agent to 30% by weight of radioactive waste liquid. This is because the glass forming agent has poor heat transfer efficiency, so if its proportion is less than this, it will be difficult to remove the decay heat in a practical scale solidified product, resulting in a significant temperature rise.
本発明の目的は、上記のような従来技術の欠点を解消し
、比較的低温で安全に溶融固化させることができ、また
放射線に対する遮蔽効果あるいは減衰効果が高く、また
伝熱放熱効果も高〈従来技術よりもはるかに減容効果が
大きい放射性廃棄物の溶融固化処理方法を提供すること
にある。The purpose of the present invention is to eliminate the above-mentioned drawbacks of the prior art, to be able to melt and solidify safely at a relatively low temperature, to have a high radiation shielding or attenuation effect, and to have a high heat transfer and heat dissipation effect. It is an object of the present invention to provide a method for melting and solidifying radioactive waste, which has a much greater volume reduction effect than conventional techniques.
［問題点を解決するための手段］
上記のような目的を達成することのできる本発明は、放
射性廃棄物と混合する固化剤として放射線遮蔽効果もし
くは減衰効果を存する低融点の金属もしくは金属化合物
を用いる点に大きな特徴があり、それらを金属製のルツ
ボ中に供給した後、マイクロ波を印加して加熱溶融し、
その後、冷却固化するようにした固化処理方法である。[Means for Solving the Problems] The present invention, which can achieve the above objects, uses a low melting point metal or metal compound that has a radiation shielding effect or attenuation effect as a solidifying agent to be mixed with radioactive waste. The main feature is that they are used, after being fed into a metal crucible, they are heated and melted by applying microwaves.
This is a solidification treatment method in which the material is then cooled and solidified.
低融点の金属もしくは金属化合物としては例えば金属鉛
、酸化鉛、酸化アンチモン、酸化ビスマス等、約１００
０℃以下の融点あるいは作業温度を呈する物質の粉体も
しくは粒体が用いられる。Examples of low melting point metals or metal compounds include metallic lead, lead oxide, antimony oxide, bismuth oxide, etc.
A powder or granule of a substance exhibiting a melting point or working temperature of 0° C. or lower is used.
［作用］
マイクロ波を印加することによって上記のような被処理
物は比較的低い温度で溶融し、その後冷却することによ
って安定した固化体を得ることができる。[Function] By applying microwaves, the object to be treated as described above is melted at a relatively low temperature, and then a stable solidified body can be obtained by cooling.
前記のような低融点の金属もしくは金属化合物は、放射
線減衰効果が高く、特に金属鉛や酸化鉛を用いれば極め
て良好な放射線遮蔽効果が得られる。また伝熱性も良好
であるため、固化体内部で発生した崩壊熱に基づく自己
発熱は速やかに外部に放散され内部温度の上昇を抑える
ことができる。The above-mentioned low melting point metals or metal compounds have a high radiation attenuation effect, and particularly when metal lead or lead oxide is used, an extremely good radiation shielding effect can be obtained. In addition, since the heat conductivity is good, self-heat generation based on decay heat generated inside the solidified body is quickly dissipated to the outside, and a rise in internal temperature can be suppressed.
本発明によれば、例えば放射性廃液７０重量％に対して
約３０重量％の低融点の金属もしくは金属化合物を用い
て良好な固化体が得られる。According to the present invention, a good solidified body can be obtained by using, for example, about 30% by weight of a low melting point metal or metal compound with respect to 70% by weight of radioactive waste liquid.
［実施例］
第１図は本発明に係る溶融固化処理工程の一例を示すフ
ローチャートである。液体あるいは固体の放射性廃棄物
と放射線遮蔽効果もしくは減衰効果を有する低融点の金
属もしくは金属化合物の粉体あるいは粒体とは、それぞ
れ対応する供給装置１０．１２によりマイクロ波溶融炉
１４内の金属製ルツボ中に供給される。ここで低融点の
金属もしくは金属化合物とは例えば金属鉛、酸化鉛、酸
化アンチモン、酸化ビスマスのような約１０００℃以下
の融点または作業温度を有する物質である。金属製のル
ツボとしては、例えばステンレス製のルツボ、あるいは
ステンレス製のルツボの内側にセラミック・ライニング
を行ったもの等が用いられる。マイクロ波溶融炉１４は
連続炉でもよいしバンチ炉でもよい、この溶融炉１４内
はマイクロ波発振装置１６から印加されたマイクロ波に
よって使用している低融点の金属もしくは金属化合物の
融点もしくは作業温度以上の温度に加熱される。これに
よって金属製のルツボ中の放射性廃棄物と低融点の金属
もしくは金属化合物は加熱溶融され均一に混合し、その
後冷却することによって良好な固化体となる。[Example] FIG. 1 is a flowchart showing an example of a melt-solidification process according to the present invention. Liquid or solid radioactive waste and powders or granules of low-melting metals or metal compounds having a radiation shielding or attenuation effect are transported into the microwave melting furnace 14 by the respective feeding devices 10.12. fed into the crucible. Here, the metal or metal compound with a low melting point is a substance having a melting point or working temperature of about 1000° C. or less, such as lead metal, lead oxide, antimony oxide, and bismuth oxide. As the metal crucible, for example, a stainless steel crucible or a stainless steel crucible with a ceramic lining inside is used. The microwave melting furnace 14 may be a continuous furnace or a bunch furnace, and the inside of this melting furnace 14 is heated by microwaves applied from a microwave oscillator 16 to control the melting point or working temperature of the low melting point metal or metal compound being used. It is heated to a temperature higher than that. As a result, the radioactive waste and the low-melting point metal or metal compound in the metal crucible are heated and melted and mixed uniformly, and then cooled to form a good solidified body.
溶融固化された固化体の断面の一例を第２図に示す、こ
こで金属製のルツボ２０はステンレスからなり、その内
面にセラミック・ライニング２２を施したものである。An example of the cross section of the melted and solidified body is shown in FIG. 2, in which a metal crucible 20 is made of stainless steel and has a ceramic lining 22 on its inner surface.
低融点の金属もしくは金属化合物２４が固化した中で、
放射性廃棄物２６が分散埋設された状態となる。もちろ
ん低融点の金属もしくは金属化合物２４と放射性廃棄物
２６との境界にはそれぞれ含を物質による混合物質や化
合物質が生じることもありうる。このようにして放射性
廃棄物２６は低融点の金属もしくは金属化合物２４によ
って覆われ固められた構造となり、安定した固化体が得
られることになる。While the low melting point metal or metal compound 24 is solidified,
The radioactive waste 26 is now dispersed and buried. Of course, at the boundary between the low-melting-point metal or metal compound 24 and the radioactive waste 26, a mixed substance or a compound substance may be generated, each containing a substance containing a substance. In this way, the radioactive waste 26 has a solidified structure covered with the metal or metal compound 24 having a low melting point, and a stable solidified body is obtained.
なお本発明においてルツボとして金属製のものを用いて
いるのは、それによってマイクロ波の漏洩を防止するこ
とができるからである。またその内側にセラミック・ラ
イニングを施すとマイクロ波加熱効率を一層向上させる
ことができる。In the present invention, a metal crucible is used because it can prevent leakage of microwaves. Moreover, if a ceramic lining is provided inside the microwave heating efficiency can be further improved.
次に模擬廃棄物として放射性廃棄物の代わりに炭酸ナト
リウムを用いて固化処理した実験例について述べる。Next, we will discuss an experimental example in which sodium carbonate was used as a simulated waste instead of radioactive waste.
［実験例コ
炭酸ナトリウムを７０重量％、酸化鉛を３０重量％とい
う割合の試料を、２４５０ Ｍ ｔｌｚのマイクロ波を
用いた５ｋＷのマイクロ波溶融炉の中に連続的に供給し
、マイクロ波を印加して約８３０〜９００℃に加熱した
。これにより被処理物を溶融し、その後冷却固化するこ
とによって１時間あたり４ｋｇの固化体を得ることがで
きた。この固化体は空気中に長時間放置しても極めて安
定であった。[Experimental Example] A sample containing 70% by weight of sodium carbonate and 30% by weight of lead oxide was continuously fed into a 5kW microwave melting furnace using microwaves of 2450 Mtlz. and heated to about 830-900°C. In this way, the material to be treated was melted and then cooled and solidified, thereby making it possible to obtain 4 kg of solidified material per hour. This solidified material was extremely stable even when left in air for a long time.
低融点である酸化鉛の量を小さな重量％値から徐々に増
加させて固化体を作成すると、空気中（２０℃の室内）
に３０日間放置しても潮解しない点が見出せる。それが
酸化鉛３０重量％、放射性廃棄物７０重量％の点である
。When a solidified substance is created by gradually increasing the amount of lead oxide, which has a low melting point, from a small weight percent value, it
It can be seen that it does not deliquesce even if left for 30 days. That is 30% by weight of lead oxide and 70% by weight of radioactive waste.
低融点である酸化鉛をこれ以上増加させてもよいが増量
となるので好ましくない。It is possible to increase lead oxide, which has a low melting point, by more than this, but this is not preferable because it increases the amount.
［発明の効果］
本発明は上記のように放射性廃棄物を固化処理する物質
として低融点の金属もしくは金属化合物を用いているた
め、約１０００℃以下の比較的低い温度での加熱で安定
した溶融固化体を作ることができるという優れた効果を
存する。[Effects of the Invention] As described above, the present invention uses a metal or metal compound with a low melting point as a substance for solidifying radioactive waste, so it can be melted stably by heating at a relatively low temperature of about 1000°C or less. It has the excellent effect of being able to form a solidified body.
低融点の金属もしくは金属化合物として放射線遮蔽効果
のある、もしくは放射線減衰効果が高い物質を用いてい
るため、得られた固化体は放射線遮蔽効果が生じ、また
伝熱効果も高いため崩壊熱に基づく自己発熱を伴う廃棄
物であっても内部で発生する熱を効率よく放散すること
ができ、温度上昇を抑えるることができる効果もある。Because we use a substance with a radiation shielding effect or a high radiation attenuation effect as a metal or metal compound with a low melting point, the obtained solidified body has a radiation shielding effect and also has a high heat transfer effect, so it is based on decay heat. Even if the waste generates heat on its own, the heat generated inside can be efficiently dissipated, which has the effect of suppressing temperature rise.
更に本発明は、低融点の金属もしくは金属化合物を用い
たことによって減容効果が極めて高くなり、例えば従来
のガラス固化処理方法の場合に比べて半分以下の減容が
可能であるなどの優れた効果を有するものである。Furthermore, the present invention has an extremely high volume reduction effect by using a metal or metal compound with a low melting point. For example, the volume can be reduced by half or less compared to conventional vitrification treatment methods. It is effective.
第１図は本発明に係る放射性廃棄物の溶融固化処理方法
の一実施例を示すフローチャート、第２図はそれにより
得られた固化体の一例を示す説明図である。
１０．１２・・・供給装置、１４・・・マイクロ波溶融
炉、１６・・・マイクロ波発振装置、２０・・・ステン
レス類のルツボ、２２・・・セラミック・ライニング、
２４・・・低融点の金属もしくは金属化合物、２６・・
・放射性廃棄物。
特許出願人 動力炉・核燃料開発事業団間 新日
本無線株式会社FIG. 1 is a flowchart showing an embodiment of the method for melting and solidifying radioactive waste according to the present invention, and FIG. 2 is an explanatory diagram showing an example of the solidified material obtained thereby. 10.12... Supply device, 14... Microwave melting furnace, 16... Microwave oscillation device, 20... Stainless steel crucible, 22... Ceramic lining,
24...Low melting point metal or metal compound, 26...
·Radioactive waste. Patent applicant: Power Reactor and Nuclear Fuel Development Corporation New Japan Radio Co., Ltd.
Claims (1)
効果を有する低融点の金属もしくは金属化合物と放射性
廃棄物とを供給し、マイクロ波を印加して加熱溶融した
後、冷却固化することを特徴とする放射性廃棄物の溶融
固化処理方法。 ２、低融点の金属もしくは金属化合物が、金属鉛、酸化
鉛、酸化アンチモン、酸化ビスマスから選択された１種
以上の粉体もしくは粒体である特許請求の範囲第１項記
載の方法。[Claims] 1. A low melting point metal or metal compound having a radiation shielding or attenuation effect and radioactive waste are supplied into a metal crucible, and after heating and melting by applying microwaves, A method for melting and solidifying radioactive waste, characterized by cooling and solidifying it. 2. The method according to claim 1, wherein the low melting point metal or metal compound is one or more powders or granules selected from metallic lead, lead oxide, antimony oxide, and bismuth oxide.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP17610985A JPH077108B2 (en) | 1985-08-10 | 1985-08-10 | Method for melting and solidifying radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP17610985A JPH077108B2 (en) | 1985-08-10 | 1985-08-10 | Method for melting and solidifying radioactive waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6236594A true JPS6236594A (en) | 1987-02-17 |
| JPH077108B2 JPH077108B2 (en) | 1995-01-30 |
Family
ID=16007846
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP17610985A Expired - Fee Related JPH077108B2 (en) | 1985-08-10 | 1985-08-10 | Method for melting and solidifying radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH077108B2 (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015143655A (en) * | 2014-01-31 | 2015-08-06 | 初一 松本 | Apparatus for concentrating radioactively contaminated water and method for treating radioactively contaminated water using the same |
| CN113737003A (en) * | 2021-10-20 | 2021-12-03 | 辽宁石油化工大学 | Method for treating waste lead-containing glass by microwave thermal smelting |
| CN113846233A (en) * | 2021-10-20 | 2021-12-28 | 辽宁石油化工大学 | Method for directly reducing and treating waste CRT glass by utilizing microwaves |
-
1985
- 1985-08-10 JP JP17610985A patent/JPH077108B2/en not_active Expired - Fee Related
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015143655A (en) * | 2014-01-31 | 2015-08-06 | 初一 松本 | Apparatus for concentrating radioactively contaminated water and method for treating radioactively contaminated water using the same |
| CN113737003A (en) * | 2021-10-20 | 2021-12-03 | 辽宁石油化工大学 | Method for treating waste lead-containing glass by microwave thermal smelting |
| CN113846233A (en) * | 2021-10-20 | 2021-12-28 | 辽宁石油化工大学 | Method for directly reducing and treating waste CRT glass by utilizing microwaves |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH077108B2 (en) | 1995-01-30 |
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