JPS5958396A - Radioactive waste solidifying method - Google Patents
Radioactive waste solidifying methodInfo
- Publication number
- JPS5958396A JPS5958396A JP16879682A JP16879682A JPS5958396A JP S5958396 A JPS5958396 A JP S5958396A JP 16879682 A JP16879682 A JP 16879682A JP 16879682 A JP16879682 A JP 16879682A JP S5958396 A JPS5958396 A JP S5958396A
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- polymerization
- substance
- mixing
- alkaline substance
- 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
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】
[発明の技術分野]
本発明は熱硬化性樹脂を使用した放射性廃棄物の固化処
理方法に関する。Detailed Description of the Invention [Technical Field of the Invention] The present invention relates to a method for solidifying radioactive waste using a thermosetting resin.
[発明の技術的背景とその問題点]
近年、原子力発電所その他の原子力施設から発生する放
射性廃液を乾燥、粉体化し、この粉体を熱硬化性樹脂等
で固化して処理することが考えられている。[Technical background of the invention and its problems] In recent years, it has been considered to dry and powder radioactive waste fluid generated from nuclear power plants and other nuclear facilities, and to treat this powder by solidifying it with thermosetting resin, etc. It is being
しかして、放射性廃棄物中には熱硬化性樹脂の重合反応
を阻害する物質が含まれる場合があり、例えば沸騰水型
原子力発電所で発生する濃縮廃液の主成分は硫酸ナトリ
ウム(Na2SO4)であるが、この他に微量成分とし
Ca、Si、Fe、Co、Ni、Cuといった元素が往
々にして含まれており、特にCuの水酸化物が存在する
と熱硬化性樹脂の重合反応が著しく阻害されることが判
明した。However, radioactive waste may contain substances that inhibit the polymerization reaction of thermosetting resins. For example, the main component of concentrated waste liquid generated at boiling water nuclear power plants is sodium sulfate (Na2SO4). However, other trace components such as Ca, Si, Fe, Co, Ni, and Cu are often included, and the presence of Cu hydroxide significantly inhibits the polymerization reaction of thermosetting resins. It turned out that.
これは胴の水酸化物は両性的性質を有して次式のように
解離し、
Cu(OH)2■Cu+++2OH−
Cu(OH)2■CuO2−−+2H+ここで発生する
H+は、重合開始剤、重合促進剤により生ずる一次ラジ
カルおよびこれに引き続き発生する連鎖反応におけるラ
ジカルと反応してラジカルを不活性化するためであると
考えられる。This is because the hydroxide in the shell has amphoteric properties and dissociates as shown in the following formula, Cu(OH)2■Cu+++2OH- Cu(OH)2CuO2--+2H+H+ generated here initiates polymerization. This is thought to be due to the reaction with the primary radicals generated by the polymerization promoter and the radicals in the subsequent chain reaction, thereby inactivating the radicals.
このようにラジカル重合により硬化する熱硬化性樹脂は
、ラジカルと反応するH+の発生源、例えば水酸化銅が
存在する場合硬化し難く、放射性廃棄物と熱硬化性樹脂
との混合物は未重合あるいは硬化不充分のまま貯蔵容器
内に貯蔵されることになる。この混合物は未重合のまま
では放射能閉じ込め能力はほとんど期待できず、そのう
え未重合の固化剤は消防法上危険物に分類されたもので
あり、放射性廃棄物をより危険な状態におくことになる
という問題があった。Thermosetting resins that harden through radical polymerization are difficult to harden in the presence of H+ sources that react with radicals, such as copper hydroxide, and mixtures of radioactive waste and thermosetting resins may be unpolymerized or It will be stored in a storage container with insufficient hardening. If this mixture remains unpolymerized, it can hardly be expected to have the ability to trap radioactivity, and furthermore, the unpolymerized solidifying agent is classified as a dangerous substance under the Fire Service Act, so it would leave radioactive waste in an even more dangerous state. There was a problem.
[発明の目的]
本発明はこのような問題を解消するためなされれもので
、放射性廃液中に硬化反応を妨害する物質、例えば水酸
化銅が含有されていても硬化が充分になされる放射性廃
棄物の固化処理方法を提供することを目的とする。[Object of the Invention] The present invention has been made to solve these problems, and provides radioactive waste that can be sufficiently cured even if the radioactive waste liquid contains substances that interfere with the curing reaction, such as copper hydroxide. The purpose of this invention is to provide a method for solidifying materials.
[発明の概要]
すなわち本発明方法は、水酸化銅または他の両性物質を
含有する放射性廃棄物に熱硬化性樹脂及び重合開始剤等
の添加物を混合する際に、アルカリ性物質と、このアル
カリ性物質と反応せずかつ熱硬化性樹脂の重合硬化反応
を阻害しない液状物質とからなるスラリーを混合して前
記放射性廃棄物を同化することを特徴とする。[Summary of the Invention] That is, the method of the present invention involves mixing an alkaline substance and this alkaline substance when mixing additives such as a thermosetting resin and a polymerization initiator with radioactive waste containing copper hydroxide or other amphoteric substances. The method is characterized in that the radioactive waste is assimilated by mixing a slurry consisting of a liquid substance that does not react with the substance and does not inhibit the polymerization and curing reaction of the thermosetting resin.
本発明に使用する熱硬化性樹脂としては、例えば無水マ
レイン酸と無水フタル酸とをプロピレングリコールと縮
合して得られる不飽和ポリエステルにスチレンのような
単量体を混合して得られるものがあげられる。この混合
物はメチルエチルケトンパーオキサイドのような重合開
始剤とナフテン酸コバルトのような重合促進剤を添加す
ると常温で硬化反応を示す。Examples of the thermosetting resin used in the present invention include those obtained by mixing a monomer such as styrene with an unsaturated polyester obtained by condensing maleic anhydride and phthalic anhydride with propylene glycol. It will be done. This mixture exhibits a curing reaction at room temperature when a polymerization initiator such as methyl ethyl ketone peroxide and a polymerization accelerator such as cobalt naphthenate are added.
本発明に使用するアルカリ性物質としては、ナトリウム
、マグネシウム、カルシウム等の水酸化物あるいは酸化
物があげられる。Examples of the alkaline substance used in the present invention include hydroxides or oxides of sodium, magnesium, calcium, and the like.
これらは、熱硬化性樹脂の重合反応を阻害する水酸化銅
等の両性物質を中和りる働きをすると考えられる。この
アルカリ性物質は、アルカリ性物質と反応せず、かつ熱
硬化性樹脂の重合硬化反応を阻害しない、例えば石油系
溶剤のような液状物質混合してスラリー状とする。アル
カリ性物質と液状物質の混合割合は、使用するアルカリ
性物質と液状物質の種類により若干異なり、アルカリ性
物質スラリーが供給装置で移送しやすい粘度となるよう
にするのが望ましい。例えば酸化マグネシウムをアルカ
リ性物質とし、液状物質にミネラルスピリッツを便用す
る場合、混合割合はアルカ性物質:液状物質=1:2と
なるようにする。These are thought to function to neutralize amphoteric substances such as copper hydroxide that inhibit the polymerization reaction of thermosetting resins. This alkaline substance is mixed with a liquid substance such as a petroleum solvent that does not react with the alkaline substance and does not inhibit the polymerization and curing reaction of the thermosetting resin to form a slurry. The mixing ratio of the alkaline substance and the liquid substance varies slightly depending on the types of the alkaline substance and liquid substance used, and it is desirable that the alkaline substance slurry has a viscosity that makes it easy to transfer with the supply device. For example, when magnesium oxide is used as an alkaline substance and mineral spirits are used as a liquid substance, the mixing ratio should be 1:2 (alkaline substance:liquid substance).
またアルカリ性物質の添加量は水酸化銅とほぼ同当量と
なる量が好ましい。Further, the amount of the alkaline substance added is preferably approximately equivalent to that of copper hydroxide.
本発明においては、乾燥、粉末化した放射性廃棄物と、
熱硬化性樹脂と、重合開始剤と、儒号促進剤と、さらに
アルカリ性物質のスラリーとを均一に混合した後、常温
で放置させる。In the present invention, dried and powdered radioactive waste,
After a thermosetting resin, a polymerization initiator, a Confucian accelerator, and a slurry of an alkaline substance are uniformly mixed, the mixture is allowed to stand at room temperature.
[発明の実施例] 次に本発明の実施例を図面を用いて説明する。[Embodiments of the invention] Next, embodiments of the present invention will be described using the drawings.
薄膜乾燥機1により乾燥、粉末化した放射性廃棄物(硫
酸ナトリウム:水酸化銅=59:1)(60重量%を、
乾燥粉体移送フィーダ2により混合槽3に移送するとと
もに、固化剤タンク4からは熱硬化性樹脂等の固化剤を
40重量%、重合開始剤タンクからは重合開始剤(メチ
ルエチルケトンパーオキサイド)を固化剤に対し0.5
重量%、重合促進剤タンク6からは重合促進剤(ナフテ
ン酸コバルト)を固化剤に対し0.5重量%混合槽3に
送り、さらにアルカリ性物質貯蔵ホッパ7と液状物質を
ミキシング装置9に送り出してミキシングすることによ
り得られるアルカリ性物質スラリーを固化剤に対し3重
合%混合槽3に定量投入して混合槽3で混合した後、ド
ラム缶10に一定量投入した。ドラム缶10を一昼夜放
置したところ強固なプラスチック固化体が得られた。Radioactive waste (sodium sulfate: copper hydroxide = 59:1) (60% by weight) dried and powdered by thin film dryer 1,
The dry powder is transferred to the mixing tank 3 by the dry powder transfer feeder 2, and 40% by weight of a solidifying agent such as a thermosetting resin is solidified from the solidifying agent tank 4, and the polymerization initiator (methyl ethyl ketone peroxide) is solidified from the polymerization initiator tank. 0.5 for agent
From the polymerization accelerator tank 6, the polymerization accelerator (cobalt naphthenate) is sent to the mixing tank 3 in an amount of 0.5% by weight based on the solidifying agent, and further, the alkaline substance storage hopper 7 and the liquid substance are sent to the mixing device 9. A fixed amount of the alkaline substance slurry obtained by mixing was put into the mixing tank 3 at a polymerization rate of 3% relative to the solidifying agent, and after mixing in the mixing tank 3, a fixed amount was put into the drum can 10. When the drum 10 was left for a day and night, a strong plastic solidified body was obtained.
[発明の効果]
以上説明したように本発明方法によれば、水酸化銅のよ
うな重合硬化反応を阻害するものが放射性廃棄物に存在
していても硬化が十分行なわれ、強固なプラスチック固
化体が得られる。[Effects of the Invention] As explained above, according to the method of the present invention, even if substances such as copper hydroxide that inhibit the polymerization curing reaction are present in the radioactive waste, curing is carried out sufficiently, and a strong plastic solidification is achieved. You get a body.
また、熱硬化性樹脂の重合硬化反応を阻害する水酸化銅
を中和するアルカリ性物質が、スラリー状で添加されて
いるので分散性がよいという利点があり、均一に硬化し
たプラスチック固化体が得られる。In addition, an alkaline substance that neutralizes copper hydroxide, which inhibits the polymerization and curing reaction of thermosetting resins, is added in the form of a slurry, which has the advantage of good dispersibility, resulting in uniformly hardened plastic solids. It will be done.
図面は本発明の一実施例を説明するための図である。 1…………薄膜乾燥機 3…………混合槽 4…………固化剤タンク 5…………重合開始剤タンク 6…………重合促進剤タンク 7…………アルカリ性物質貯蔵ホッパ 8…………液状物質タンク 10………ドラム缶 代理人弁理士 須山 佐一 The drawings are diagrams for explaining one embodiment of the present invention. 1…………Thin film dryer 3…………Mixing tank 4…………Solidifying agent tank 5...Polymerization initiator tank 6...Polymerization accelerator tank 7……Alkaline substance storage hopper 8……Liquid substance tank 10……Drum can Representative Patent Attorney Saiichi Suyama
Claims (1)
放射性廃棄物に熱硬化性樹脂を混合する際に、アルカリ
性物質と、このアルカリ性物質と反応せずかつ熱硬化性
樹脂の重合硬化反応を阻害しない液状物質とからなるス
ラリーを混合して前記放射性廃棄物を固化することを特
徴とする放射性廃棄物の固化処理方法。When mixing a thermosetting resin with radioactive waste containing a hydroxide cylinder or a substance that dissociates to generate H+, a polymerization curing reaction between an alkaline substance and a thermosetting resin that does not react with this alkaline substance is necessary. A method for solidifying radioactive waste, comprising solidifying the radioactive waste by mixing a slurry with a liquid substance that does not inhibit the radioactive waste.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP16879682A JPS5958396A (en) | 1982-09-28 | 1982-09-28 | Radioactive waste solidifying method |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP16879682A JPS5958396A (en) | 1982-09-28 | 1982-09-28 | Radioactive waste solidifying method |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS5958396A true JPS5958396A (en) | 1984-04-04 |
JPH0151957B2 JPH0151957B2 (en) | 1989-11-07 |
Family
ID=15874629
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP16879682A Granted JPS5958396A (en) | 1982-09-28 | 1982-09-28 | Radioactive waste solidifying method |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS5958396A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS63168598A (en) * | 1986-12-30 | 1988-07-12 | 株式会社東芝 | Solidifying processing method of radioactive waste |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5322174A (en) * | 1976-08-12 | 1978-03-01 | Commissariat Energie Atomique | Method of conditioning contaminated ion exchange resins |
-
1982
- 1982-09-28 JP JP16879682A patent/JPS5958396A/en active Granted
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5322174A (en) * | 1976-08-12 | 1978-03-01 | Commissariat Energie Atomique | Method of conditioning contaminated ion exchange resins |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS63168598A (en) * | 1986-12-30 | 1988-07-12 | 株式会社東芝 | Solidifying processing method of radioactive waste |
Also Published As
Publication number | Publication date |
---|---|
JPH0151957B2 (en) | 1989-11-07 |
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