JPH0151958B2 - - Google Patents

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Publication number
JPH0151958B2
JPH0151958B2 JP57168797A JP16879782A JPH0151958B2 JP H0151958 B2 JPH0151958 B2 JP H0151958B2 JP 57168797 A JP57168797 A JP 57168797A JP 16879782 A JP16879782 A JP 16879782A JP H0151958 B2 JPH0151958 B2 JP H0151958B2
Authority
JP
Japan
Prior art keywords
alkaline substance
tank
mixing tank
radioactive waste
feeder
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.)
Expired
Application number
JP57168797A
Other languages
Japanese (ja)
Other versions
JPS5958397A (en
Inventor
Shunei Tomita
Juji Minami
Hiroyuki Matsura
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Toshiba Corp, Nippon Genshiryoku Jigyo KK filed Critical Toshiba Corp
Priority to JP16879782A priority Critical patent/JPS5958397A/en
Publication of JPS5958397A publication Critical patent/JPS5958397A/en
Publication of JPH0151958B2 publication Critical patent/JPH0151958B2/ja
Granted legal-status Critical Current

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  • Processing Of Solid Wastes (AREA)

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で放射性廃棄物を固化処
理するための装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to an apparatus for solidifying radioactive waste with 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てCa,Si,Fe,Co,
Ni,Cuといつ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 fluid generated at boiling water nuclear power plants is sodium sulfate (Na 2 SO 4 ), but other minor components include Ca, Si, Fe, Co,
Often contains elements such as Ni and Cu,
In particular, it was found that the presence of Cu hydroxide significantly inhibits the polymerization reaction of thermosetting resins.

これは銅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)2Cu+++20H- Cu(OH)2CuO2 --+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 copper hydroxide has amphoteric properties and dissociates as shown in the following formula, Cu(OH) 2 Cu ++ +20H - Cu(OH) 2 CuO 2 -- +2H + H + generated here This is thought to be due to the reaction with primary radicals generated by the polymerization initiator and polymerization accelerator 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つた。
Thermosetting resins that harden through radical polymerization are difficult to cure in the presence of sources of H + that react with radicals, such as copper hydroxide, and mixtures of radioactive waste and thermosetting resins are difficult to cure when they are not polymerized. Otherwise, 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になさ
れたもので、放射性廃棄物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
が可能である放射性廃棄物の固化処理装置を提供
することを目的とする。
[Purpose of the Invention] The present invention was made to solve these problems, and it is a radioactive waste that can be cured even if the radioactive waste contains substances that interfere with the curing reaction, such as copper hydroxide. The purpose is to provide a solidification treatment device for waste.

[発明の概要] すなわち本発明装置は、水酸化銅または他の両
性物質を含有する放射性廃液を乾燥、粉体化する
装置と、この粉体を混合槽へ移送するための乾燥
粉体移送フイーダと、この粉体および固化剤タン
ク、重合開始剤タンク、重合促進剤タンク等から
送出される固化剤、重合開始剤、重合促進剤等を
混合するための混合槽と、この混合槽に粉状のア
ルカリ性物質を供給するためのアルカリ性物質定
量供給フイーダと、このアルカリ性物質を貯蔵す
るためにアルカリ性物質貯蔵ホツパとを備えたこ
とを特徴とする。
[Summary of the Invention] That is, the apparatus of the present invention includes an apparatus for drying and powdering radioactive waste liquid containing copper hydroxide or other amphoteric substances, and a dry powder transfer feeder for transferring this powder to a mixing tank. and a mixing tank for mixing this powder with the solidifying agent, polymerization initiator, polymerization accelerator, etc. sent from the solidifying agent tank, polymerization initiator tank, polymerization accelerator tank, etc., and the powder in this mixing tank. The present invention is characterized by comprising an alkaline substance quantitative supply feeder for supplying the alkaline substance, and an alkaline substance storage hopper for storing the alkaline substance.

[発明の実施例] 次に本発明の実施例について説明する。[Embodiments of the invention] Next, examples of the present invention will be described.

第1図は本発明装置の一実施例である。 FIG. 1 shows an embodiment of the apparatus of the present invention.

本発明装置は、廃液タンク1から送られてきた
放射性廃液を乾燥、粉体化する薄膜乾燥機2と、
この粉体を混合槽3へ移送するための乾燥粉体移
送フイーダ4と、この物体および固化剤タンク
5、重合開始剤タンク6、重合促進剤タンク7か
ら送り出される熱硬化性樹脂等からなる固化剤、
メチルエチルケトンパーオキサイド等の重合開始
剤、ナフテン酸コバルト等の重合促進剤を混合す
るための混合槽3と、この混合槽3に開口して、
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の粉状のアルカル性物質を供
給するためのアルカリ性物質定量供給フイーダ8
と、このアルカリ性物質を貯蔵するためのアルカ
リ性物質貯蔵ホツパ9を備えている。なお、符号
10は禁止剤タンクであり、重合を中止する際使
用される。
The device of the present invention includes a thin film dryer 2 that dries and powderizes radioactive waste liquid sent from a waste liquid tank 1;
A dry powder transfer feeder 4 for transferring this powder to a mixing tank 3, and solidification consisting of a thermosetting resin etc. sent out from this object, a solidification agent tank 5, a polymerization initiator tank 6, and a polymerization accelerator tank 7. agent,
A mixing tank 3 for mixing a polymerization initiator such as methyl ethyl ketone peroxide and a polymerization accelerator such as cobalt naphthenate;
Alkaline substance quantitative supply feeder 8 for supplying powdered alkaline substances of hydroxides or oxides such as sodium, magnesium, calcium, etc.
and an alkaline substance storage hopper 9 for storing this alkaline substance. Note that the reference numeral 10 is an inhibitor tank, which is used when stopping polymerization.

本発明においては、廃液タンク1から送出さ
れ、薄膜乾燥機2で乾燥粉末化された放射性廃棄
物は、乾燥粉体移送フイーダ4により混合槽3ま
で移送され、ここで放射性廃棄物には固化剤、重
合開始剤および重合促進剤とともにアルカリ性物
質が混合され、混合槽3の真下に配置されたドラ
ム管(図示せず)に投入され、ほぼ一昼夜放置さ
せることによりプラスチツク固化体が得られる。
In the present invention, the radioactive waste sent from the waste liquid tank 1 and dried and powdered by the thin film dryer 2 is transferred to the mixing tank 3 by the dry powder transfer feeder 4, where the radioactive waste is treated with a solidifying agent. An alkaline substance is mixed together with a polymerization initiator and a polymerization accelerator, and the mixture is put into a drum tube (not shown) placed directly below the mixing tank 3, and left to stand for about a day and night to obtain a solidified plastic.

第2図は本発明装置の別の実施例を示すもの
で、アルカリ性物質定量供給フイーダ8は乾燥粉
体移送フイーダ4に開口して取付けられている。
なお符号11は乾燥粉体貯蔵ホツパである。
FIG. 2 shows another embodiment of the apparatus of the present invention, in which an alkaline substance quantitative supply feeder 8 is opened and attached to the dry powder transfer feeder 4.
Note that the reference numeral 11 is a dry powder storage hopper.

この装置によれば、一旦アルカリ性物質は乾燥
粉末である放射性廃棄物と混合されてから混合槽
に添加されるので、分散性がよくなり均一に硬化
できる。
According to this device, the alkaline substance is mixed with radioactive waste in the form of dry powder and then added to the mixing tank, so that the alkaline substance has good dispersibility and can be uniformly cured.

[発明の効果] 本発明装置によれば、水酸化銅のような熱硬化
性樹脂の重合硬化反応を阻害するものが存在して
いても硬化が十分行なわれ、強固なプラスチツク
固化体を得ることができる。
[Effects of the Invention] According to the apparatus of the present invention, even if there is a substance that inhibits the polymerization and curing reaction of the thermosetting resin, such as copper hydroxide, curing is carried out sufficiently and a strong solidified plastic product can be obtained. Can be done.

また、アルカリ性物質定量供給フイーダにより
放射性廃棄物中の両性化合物の有無、種類、濃度
等に最適なアルカリ性物質を所定量供給添加でき
るので無駄のない処理を行なうことができる。ま
た、アルカリ性物質定量供給フイーダを乾燥粉体
移送フイーダに開口して取付けることにより、ア
ルカリ性物質が均一に分散して添加されることに
なるので均一に硬化したプラスチツク固化体が得
られる。
In addition, since the alkaline substance quantitative supply feeder can supply and add a predetermined amount of alkaline substance that is optimal for the presence, type, concentration, etc. of amphoteric compounds in the radioactive waste, waste-free processing can be performed. Furthermore, by attaching the alkaline substance quantitative supply feeder to the dry powder transfer feeder with an opening, the alkaline substance is added in a uniformly dispersed manner, so that a uniformly hardened plastic solidified body can be obtained.

【図面の簡単な説明】[Brief explanation of drawings]

第1図、第2図は本発明装置の一実施例を概略
的に示す図である。 1……廃液タンク、2……薄膜乾燥機、3……
混合槽、4……乾燥粉体移送フイーダ、5……固
化剤タンク、6……重合開始剤タンク、7……重
合促進剤タンク、8……アルカリ性物質定量供給
フイーダ、9……アルカリ性物質貯蔵ホツパ。
FIGS. 1 and 2 are diagrams schematically showing an embodiment of the apparatus of the present invention. 1... Waste liquid tank, 2... Thin film dryer, 3...
Mixing tank, 4... Dry powder transfer feeder, 5... Solidifying agent tank, 6... Polymerization initiator tank, 7... Polymerization accelerator tank, 8... Alkaline substance quantitative supply feeder, 9... Alkaline substance storage Hotupa.

Claims (1)

【特許請求の範囲】 1 水酸化銅または解離してH+を発生する物質
を含有する放射性廃液を乾燥、粉体化する装置
と、この粉体を混合槽へ移送するための乾燥粉体
移送フイーダと、この粉体および固化剤タンク、
重合開始剤タンク、重合促進剤タンク等から送出
される固化剤、重合開始剤、重合促進剤等を混合
するための混合槽と、この混合槽に粉状のアルカ
リ性物質を供給するためのアルカリ性物質定量供
給フイーダと、このアルカリ性物質を貯蔵するた
めのアルカリ性物質貯蔵ホツパとを備えたことを
特徴とする放射性廃棄物の固化処理装置。 2 アルカリ性物質定量供給フイーダは混合槽に
開口してアルカリ性物質が直接混合槽に添加され
るようになつている特許請求の範囲第1項記載の
放射性廃棄物の固化処理装置。 3 アルカリ性物質定量供給フイーダは乾燥粉体
移送フイーダに開口してアルカリ性物質は一旦乾
燥粉体と混合されてから混合槽に添加されるよう
になつている特許請求の範囲第1項記載の放射性
廃棄物の固化処理装置。
[Claims] 1. A device for drying and pulverizing radioactive waste liquid containing copper hydroxide or a substance that dissociates to generate H + , and a dry powder transfer for transferring this powder to a mixing tank. feeder, this powder and solidifying agent tank,
A mixing tank for mixing the solidifying agent, polymerization initiator, polymerization accelerator, etc. delivered from the polymerization initiator tank, polymerization accelerator tank, etc., and an alkaline substance for supplying powdered alkaline substances to this mixing tank. A radioactive waste solidification processing apparatus characterized by comprising a fixed quantity supply feeder and an alkaline substance storage hopper for storing this alkaline substance. 2. The radioactive waste solidification treatment apparatus according to claim 1, wherein the alkaline substance quantitative supply feeder opens into the mixing tank so that the alkaline substance is directly added to the mixing tank. 3. Radioactive waste according to claim 1, wherein the alkaline substance quantitative supply feeder is opened to the dry powder transfer feeder, and the alkaline substance is once mixed with the dry powder and then added to the mixing tank. Material solidification processing equipment.
JP16879782A 1982-09-28 1982-09-28 Radioactive waste solidifying device Granted JPS5958397A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP16879782A JPS5958397A (en) 1982-09-28 1982-09-28 Radioactive waste solidifying device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP16879782A JPS5958397A (en) 1982-09-28 1982-09-28 Radioactive waste solidifying device

Publications (2)

Publication Number Publication Date
JPS5958397A JPS5958397A (en) 1984-04-04
JPH0151958B2 true JPH0151958B2 (en) 1989-11-07

Family

ID=15874648

Family Applications (1)

Application Number Title Priority Date Filing Date
JP16879782A Granted JPS5958397A (en) 1982-09-28 1982-09-28 Radioactive waste solidifying device

Country Status (1)

Country Link
JP (1) JPS5958397A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH07119832B2 (en) * 1986-12-30 1995-12-20 株式会社東芝 Method for solidifying radioactive waste
JPH0429098A (en) * 1990-05-25 1992-01-31 Toshiba Corp Method for solidifying radioactive waste with plastic

Citations (2)

* Cited by examiner, † Cited by third party
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
JPS5696300A (en) * 1979-12-28 1981-08-04 Ebara Mfg Method and apparatus for solidifying radioactive waste

Patent Citations (2)

* Cited by examiner, † Cited by third party
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
JPS5696300A (en) * 1979-12-28 1981-08-04 Ebara Mfg Method and apparatus for solidifying radioactive waste

Also Published As

Publication number Publication date
JPS5958397A (en) 1984-04-04

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