JPS6117995A - Method of treating radioactive ion exchange resin - Google Patents

Method of treating radioactive ion exchange resin

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Publication number
JPS6117995A
JPS6117995A JP59137308A JP13730884A JPS6117995A JP S6117995 A JPS6117995 A JP S6117995A JP 59137308 A JP59137308 A JP 59137308A JP 13730884 A JP13730884 A JP 13730884A JP S6117995 A JPS6117995 A JP S6117995A
Authority
JP
Japan
Prior art keywords
resin
ion exchange
exchange resin
radioactive
inorganic adsorbent
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
Application number
JP59137308A
Other languages
Japanese (ja)
Inventor
鬼沢 秀夫
柏井 俊彦
船越 俊夫
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries Ltd
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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP59137308A priority Critical patent/JPS6117995A/en
Publication of JPS6117995A publication Critical patent/JPS6117995A/en
Pending legal-status Critical Current

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  • Treatment Of Water By Ion Exchange (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、原子カプラントから排出さnる放射性物質を
捕捉して放射能を帯びたイオン交換性樹脂の合目的な処
理方法に関する。
DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a method for the purposeful treatment of radioactive ion exchange resins by capturing radioactive substances discharged from atomic couplants.

(従来の技術) 放射性イオン交換樹脂(以下簡単のため単に@樹脂”と
記す。)の処理方法は種々検討さnているが、実用化に
至ったものはまだないのが冥情である。
(Prior Art) Various methods for treating radioactive ion exchange resins (hereinafter simply referred to as @resin for simplicity) have been studied, but unfortunately, none has yet been put to practical use.

代表的な方法とその欠点を挙げると下記の通りである。Typical methods and their drawbacks are listed below.

(リ 焼却法・・・・・文字通り樹脂を焼却する方法で
あるが、樹脂中の含有放射能レベルが高い場合は、燃焼
排ガス中に含ま扛る放射能量も増大するので、排ガス処
理装置には過大な放射能除染性能が要求されることとな
る。すなわち排ガス処理装置が複雑・大規模化する。ま
几焼却灰の放射性物質濃度が高くなり、その取扱いが容
易でない。
(Incineration method: Literally a method of incinerating resin, but if the radioactivity level contained in the resin is high, the amount of radioactivity contained in the combustion exhaust gas will also increase, so it is not recommended for exhaust gas treatment equipment. Excessive radioactive decontamination performance will be required.In other words, the exhaust gas treatment equipment will become complicated and large-scale.The concentration of radioactive substances in the incineration ash will increase, making it difficult to handle.

(2)熱分解法・・・・・酸素の供給を断って高温で加
熱分解させ、その後分解ガスを燃焼させる方法であるが
、焼却法に比べ煤塵が少ないとはいえ、熱分解工程が余
分に必要であり、また生成物の放射性物質濃度が高い事
には変りない。
(2) Pyrolysis method: This is a method in which the supply of oxygen is cut off and the decomposition is carried out at high temperatures, and then the decomposed gas is combusted.Although it produces less dust compared to the incineration method, the pyrolysis step is redundant. This does not change the fact that the radioactive material concentration in the product is high.

(3)化学分解法・・・・・化学薬品との化学反応にx
!ll樹脂を酸化分解するものであるが、強力な酸及び
酸化剤を高温で取扱うので装置構成材料の腐食が問題と
なる。
(3) Chemical decomposition method: x for chemical reactions with chemicals
! This method oxidizes and decomposes 11 resin, but since strong acids and oxidizing agents are handled at high temperatures, corrosion of the equipment's constituent materials becomes a problem.

(4)  M接置化法・・・・・セメント、アスファル
ト、ポリマー等で樹脂k[接円化する方法であるが、樹
脂が有機物質であるため、固化体が長期間の安定性に欠
ける。
(4) M-contacting method: This is a method of encircling resin K with cement, asphalt, polymers, etc., but since the resin is an organic substance, the solidified product lacks long-term stability. .

(発明が解決しようとする問題点) 本発明は上記従来法の欠点全解消するためになさt′し
たものであって、比較的高レベルの樹脂を焼却法で処理
する場合において、焼却灰の放射付物質濃度を低減させ
、焼却炉の排ガス中に含まれる放射能を少なくして排ガ
ス処理システムにかかる負担を軽減し、高レベルの放射
性物質は信頼性の高い同化体内に閉じ込める方法を提供
せんとするものである。
(Problems to be Solved by the Invention) The present invention has been made in order to eliminate all the drawbacks of the above-mentioned conventional methods. It reduces the concentration of radioactive materials, reduces the amount of radioactivity contained in the incinerator exhaust gas, reduces the burden on the exhaust gas treatment system, and provides a reliable way to confine high-level radioactive materials in assimilators. That is.

(問題点全解決するための手段) 本発明は、樹脂が保育している放射性物質(Os−13
7、Elr−90、Co−6Dなど)全、ゼオライトの
ような無機吸着剤に移行させ、保育放射能の減少した樹
脂は焼却炉で焼却し、放射能全吸着した無機物は水熱合
成反応にエリ岩石化し、信頼性の高い固化体とするもの
である。
(Means for solving all the problems) The present invention solves the problem of radioactive substances (Os-13
7, Elr-90, Co-6D, etc.), transferred to an inorganic adsorbent such as zeolite, and the resin with reduced radioactivity is incinerated in an incinerator, and the inorganic material that has completely absorbed radioactivity is subjected to a hydrothermal synthesis reaction. This is to turn it into rock and make it into a highly reliable solidified body.

すなわち、本発明は放射性イオン交換樹脂の保有してい
る放射性物質を、溶媒を媒体として無機吸着剤に移行さ
せ、保育放射能の減少したイオン交換樹脂は焼却炉で焼
却し、放射能を吸着した無機吸着剤は水熱台底によって
岩石化することを特徴とする放射性イオン交換樹脂の処
理方法である。
That is, the present invention transfers the radioactive substances contained in the radioactive ion exchange resin to an inorganic adsorbent using a solvent as a medium, and the ion exchange resin whose nursery radioactivity has decreased is incinerated in an incinerator to adsorb the radioactivity. Inorganic adsorbent is a treatment method for radioactive ion exchange resin characterized by turning it into rock by hydrothermal treatment.

本発明は、概略的に云えば、無機吸着剤による吸着技術
、焼却技術、水熱合成技術を組合せた技術である。
Broadly speaking, the present invention is a technology that combines an adsorption technology using an inorganic adsorbent, an incineration technology, and a hydrothermal synthesis technology.

吸着技術、焼却技術は周知な技術であるので説明を省略
するが、水熱合成反応とは水の臨界点以上の圧力、温度
条件下で物質の合成及び結晶の育成を行なう方法である
。臨界点に保持することにより、溶解した鉱物成分のイ
オン反応が著しく加速さ扛、結晶核の析出・成長が殆ん
ど瞬間的に行なわしるため、地質学的長期間を経て完成
さnる岩石を人工的に短時間で造ることができることに
なる技術である。
Adsorption technology and incineration technology are well-known technologies, so their explanations will be omitted. Hydrothermal synthesis reaction is a method of synthesizing substances and growing crystals under conditions of pressure and temperature above the critical point of water. By holding it at a critical point, the ionic reaction of the dissolved mineral components is significantly accelerated, and the precipitation and growth of crystal nuclei occur almost instantaneously, so it is completed over a geologically long period of time. This technology allows rocks to be created artificially in a short period of time.

本発明に工nば、焼却炉へ供給さ扛る樹脂は放射性物質
の大部分を抜き取られた後であるので、その後の処置が
容易、すなわち排ガス処理と焼却灰の取扱いが容易とな
る。また無機吸着剤であるゼオライトは水熱合成に適し
た物質であり、良質の(強度大、放射能浸出率極小、長
期安定)の岩石となる。
According to the present invention, since most of the radioactive materials have been removed from the resin supplied to the incinerator, subsequent treatment becomes easy, that is, exhaust gas treatment and incineration ash handling become easy. In addition, zeolite, which is an inorganic adsorbent, is a material suitable for hydrothermal synthesis and produces rocks of high quality (high strength, minimal radioactive leaching rate, long-term stability).

以下、本発明の一実施態様につき第1図を参照しながら
説明する◎ 樹脂1はまず樹脂受はタンク2に受け、所定量全樹脂供
給ポンプ3により、樹脂充填塔4に装填する。樹脂充填
塔4は樹脂の受は人n口、排出口のほか抽出液が循環す
るための入口と出口を備えている。抽出液は種々の溶液
が考えら詐るが酒石酸塩溶液が適している。抽出液は抽
出液循環ポンプ8により、樹脂充填塔4→無機吸着剤光
填塔6→抽出液タンク7→抽出液循環ポンプ8の閉ルー
プを循環する。無機吸着剤はゼオライトが適しており、
図中5のラインから無機吸着剤充填塔6に所定量装填さ
扛る。前記閉ループで抽出液を所定時間循環させると樹
脂が保有していた放射性物質(Os−137,5r−9
0等)は樹脂1エク抽出液中に離脱し、七扛らは無機吸
着剤(ゼオライト)に吸着さnる。このようにして大部
分の放射能は樹脂から無機吸着剤へ移行するので、その
後樹脂1は樹脂充填塔4の下部から排出し、焼却炉樹脂
受はタンク11へ送らn、その後焼却炉樹脂供給ポンプ
12により焼却炉13へ供給さn焼却さnる。
Hereinafter, one embodiment of the present invention will be explained with reference to FIG. 1. ◎ The resin 1 is first received in a resin receiver tank 2, and a predetermined amount of resin is loaded into a resin packed tower 4 by a total resin supply pump 3. The resin packed tower 4 has a resin receiving port, a discharge port, and an inlet and an outlet for circulating the extract. Various solutions can be used as the extract, but a tartrate solution is suitable. The extract is circulated by the extract circulation pump 8 in a closed loop of the resin-packed column 4 -> the inorganic adsorbent light-packed tower 6 -> the extract tank 7 -> the extract circulation pump 8 . Zeolite is suitable as an inorganic adsorbent.
A predetermined amount of inorganic adsorbent is loaded into the inorganic adsorbent packed tower 6 from the line 5 in the figure. When the extract is circulated in the closed loop for a predetermined period of time, the radioactive substances (Os-137, 5r-9) held in the resin are removed.
0, etc.) are separated into the resin extract, and the 70% are adsorbed to an inorganic adsorbent (zeolite). In this way, most of the radioactivity is transferred from the resin to the inorganic adsorbent, so the resin 1 is then discharged from the lower part of the resin packed tower 4, the incinerator resin receiver is sent to the tank 11, and then the incinerator resin is supplied. It is supplied to an incinerator 13 by a pump 12 and is incinerated.

第1図は流動層式の焼却炉の場合について示しであるが
、細形式の焼却炉であっても本発明の趣旨は損なわnな
い。流動層式の焼却炉13では下部より燃焼用空気14
が吹き込まn流動層内で樹脂は効率良〈燃焼さnる。灰
分は焼却炉13の上部よりサイクロン15に送らn、灰
の大部分はサイクロン15にて排ガス中より分離補集さ
nる。その後排ガスは排ガス処理装置16(湿式処理装
置であるベンチュリ・スクラバ及びガラスファイバーな
ど金剛いた高能率突気フィルター等で構成さnる。)に
Xり固形分及び有害ガスを除去した後排ガス17となり
大気に放出さnる。一方、サイクロン15で捕集した焼
却灰はサイクロン15下部より排出し、焼却灰固化装置
18にて固化さn固化体19となる。ここで固化装置と
しては、種々の公知のもの(セメント固化、プラスチッ
ク固化、岩石化等々)のいず牡てもよい。
Although FIG. 1 shows the case of a fluidized bed type incinerator, the spirit of the present invention will not be impaired even if the incinerator is of a narrow type. In a fluidized bed type incinerator 13, combustion air 14 is introduced from the bottom.
The resin is blown into the fluidized bed and burns efficiently. Ash is sent from the upper part of the incinerator 13 to a cyclone 15, and most of the ash is separated and collected from the exhaust gas in the cyclone 15. After that, the exhaust gas is passed through the exhaust gas treatment device 16 (composed of a wet treatment device such as a Venturi scrubber and a high-efficiency gust filter made of glass fiber, etc.) to remove solids and harmful gases, and then becomes the exhaust gas 17. released into the atmosphere. On the other hand, the incinerated ash collected by the cyclone 15 is discharged from the lower part of the cyclone 15, and is solidified into a solidified body 19 in the incinerated ash solidification device 18. Here, the solidification device may be any of various known devices (cement solidification, plastic solidification, rock solidification, etc.).

一方無機吸着剤充填塔6において、放射性物質(Os−
137,5r−90等)を吸着した無機吸着剤(ゼオラ
イト)ハ、岩石化装置9へ送らnる・この岩石化装置9
は水熱会成反応を利用したものであり、前記ゼオライト
にNaOH水溶液全小量加えよく練り混ぜた後、水熱ホ
ットプレスに充填し、所定時間水熱条件下温度(200
℃〜300℃、圧力〜300 kg/ctn” Gに)
に保持することにより良質の固化体10を得る。
On the other hand, in the inorganic adsorbent packed tower 6, a radioactive substance (Os-
137, 5r-90, etc.) is sent to the petrification device 9. This petrification device 9
utilizes a hydrothermal formation reaction, in which a small amount of NaOH aqueous solution is added to the zeolite and mixed well, then filled into a hydrothermal hot press and heated at a temperature (200
℃~300℃, pressure~300 kg/ctn”G)
A high quality solidified body 10 can be obtained by holding the solidified body 10 at

(効果) 本発明は、前記した方法とその作用により下記の効果が
得らnる。
(Effects) The present invention provides the following effects through the above-described method and its effects.

(1)焼却炉へ供給さ扛る樹脂は大部分の放射能を抜き
散った後のものであるからその後処理が極めて容易とな
る。具体的には ■ 燃焼排ガス中に一@まする放射性物質が小量となる
ので排ガス処理装置に要求さ扛る放射能除去性能は低く
て済む。すなわち簡単な装置で済む。
(1) Since most of the radioactivity has been removed from the resin supplied to the incinerator, subsequent processing is extremely easy. Specifically, ■ Since the amount of radioactive materials in the combustion exhaust gas is small, the radioactivity removal performance required of the exhaust gas treatment device is low. In other words, a simple device is sufficient.

■ 焼却灰の放射性物質濃度が低いのでその取扱が容易
と力る。(焼却灰の固化装置も楽になる。) (2)樹脂から抜き取ら扛た放射性物質はゼオライトに
吸着さA、さらにそnc)は強度、放射能の浸出率、長
期安定性に優nた岩石体にすることができる。
■ The low concentration of radioactive substances in incinerated ash makes it easy to handle. (It also makes it easier to solidify incinerated ash.) (2) The radioactive substances extracted from the resin are adsorbed to zeolite. It can be done.

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

第1図は本発明の一実施態様のフロー全示す。 復代理人  内 1)  明 復代理人  萩 原 亮 − FIG. 1 shows the entire flow of one embodiment of the present invention. Sub-agent: 1) Akira Sub-agent Ryo Hagi Hara -

Claims (1)

【特許請求の範囲】[Claims] 放射性イオン交換樹脂の保有している放射性物質を溶媒
を媒体として無機吸着剤に移行させ、保有放射能の減少
したイオン交換樹脂は焼却炉で焼却し、放射能を吸着し
た無機吸着剤は水熱合成によつて岩石化することを特徴
とする放射性イオン交換樹脂の処理方法。
The radioactive substances contained in the radioactive ion exchange resin are transferred to an inorganic adsorbent using a solvent as a medium, and the ion exchange resin whose radioactivity has decreased is incinerated in an incinerator, and the inorganic adsorbent that has absorbed radioactivity is transferred to an inorganic adsorbent using a solvent. A method for processing radioactive ion exchange resin, which is characterized by turning into rock through synthesis.
JP59137308A 1984-07-04 1984-07-04 Method of treating radioactive ion exchange resin Pending JPS6117995A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59137308A JPS6117995A (en) 1984-07-04 1984-07-04 Method of treating radioactive ion exchange resin

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59137308A JPS6117995A (en) 1984-07-04 1984-07-04 Method of treating radioactive ion exchange resin

Publications (1)

Publication Number Publication Date
JPS6117995A true JPS6117995A (en) 1986-01-25

Family

ID=15195645

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59137308A Pending JPS6117995A (en) 1984-07-04 1984-07-04 Method of treating radioactive ion exchange resin

Country Status (1)

Country Link
JP (1) JPS6117995A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH03113089U (en) * 1990-03-02 1991-11-19
WO1995034900A1 (en) * 1994-06-14 1995-12-21 Siemens Aktiengesellschaft Method of reducing the volume of a mixture of resin powder and inert synthetic fibres
WO2001023113A1 (en) * 1999-09-28 2001-04-05 Bayer Aktiengesellschaft Method for conditioning ion exchange resins

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH03113089U (en) * 1990-03-02 1991-11-19
WO1995034900A1 (en) * 1994-06-14 1995-12-21 Siemens Aktiengesellschaft Method of reducing the volume of a mixture of resin powder and inert synthetic fibres
WO2001023113A1 (en) * 1999-09-28 2001-04-05 Bayer Aktiengesellschaft Method for conditioning ion exchange resins

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