KR950004288A - Treatment method of radioactive liquid - Google Patents

Treatment method of radioactive liquid Download PDF

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Publication number
KR950004288A
KR950004288A KR1019940018028A KR19940018028A KR950004288A KR 950004288 A KR950004288 A KR 950004288A KR 1019940018028 A KR1019940018028 A KR 1019940018028A KR 19940018028 A KR19940018028 A KR 19940018028A KR 950004288 A KR950004288 A KR 950004288A
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KR
South Korea
Prior art keywords
ion exchange
radioactive
exchange resin
nuclide
radionuclide
Prior art date
Application number
KR1019940018028A
Other languages
Korean (ko)
Inventor
앤토니 배터글리아 조셉
게리 코놉카 조지
Original Assignee
다니엘 씨. 에이블스
웨스팅하우스 일렉트릭 코포레이션
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 다니엘 씨. 에이블스, 웨스팅하우스 일렉트릭 코포레이션 filed Critical 다니엘 씨. 에이블스
Publication of KR950004288A publication Critical patent/KR950004288A/en

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/12—Processing by absorption; by adsorption; by ion-exchange
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
    • B01J49/00—Regeneration or reactivation of ion-exchangers; Apparatus therefor
    • C—CHEMISTRY; METALLURGY
    • C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02F1/00—Treatment of water, waste water, or sewage
    • C02F1/28—Treatment of water, waste water, or sewage by sorption

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Hydrology & Water Resources (AREA)
  • Environmental & Geological Engineering (AREA)
  • Water Supply & Treatment (AREA)
  • Treatment Of Water By Ion Exchange (AREA)
  • Treatment Of Liquids With Adsorbents In General (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)

Abstract

본 발명은 핵시설물에서 폐기시키기 위한 고체 방사성 폐기물의 부피를 최소화하는 방사성 액체의 처리방법을 제공한다. 상기 방법은 흡착 매질, 바람직하게는 이온 교환 매질은 보존하면서 폐기시키기 위한 방사성 고체 폐기물의 양은 최소로 하는 신규한 배열의 2단계 흡착 공정, 바람직하게는 2단계 이온 교환 공정의 조합에 의해 방사성 액체를 처리함을 포함한다.The present invention provides a method for treating radioactive liquids that minimizes the volume of solid radioactive waste for disposal in nuclear facilities. The process utilizes a novel arrangement of radioactive liquids by a combination of a novel arrangement of two stage adsorption processes, preferably two stage ion exchange processes, which minimizes the amount of radioactive solid waste for disposal while preserving the adsorption medium, preferably the ion exchange medium. Processing.

Description

방사성 액체의 처리 방법Treatment method of radioactive liquid

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음Since this is an open matter, no full text was included.

제1도는 본 발명에 따른 방법을 예시하는 흐름도이고, 제2도는 본 발명에 따른 방법을 수행하기 위해 개장된 현행 방사성 액체 공정 시스템의 흐름도이다.1 is a flow chart illustrating a method according to the invention, and FIG. 2 is a flow diagram of a current radioactive liquid processing system adapted for carrying out the method according to the invention.

Claims (7)

방사성 원자핵종 및 비-방사성 원자핵종을 함유하는 방사성 액체를 이온 교환 수지와 접촉시켜 상기 액체로부터 상기 방사성 원자해종 및 비-방사성 원자핵종을 함유하는 사용된 이온 교환 수지를 형성하도록 노출시키고; 상기 사용된 이온 이온 교환 수지에 함유된 상기 방사성 원자핵종 및 비-방사성 원자핵종을 사용된 재생제 용액으로 방출시키기 위해 상기 사용된 이온 교환 수지를 재생시키고; 방사성 원자핵종 및 비-방사성 원자핵종을 포함하는 상기 사용된 재생제 용액을 원자핵종-특이성 매질과 접촉시켜 상기 방사성 원자핵종을 상기 사용된 재생제 용액으로부터 선택적으로 분리시키고, 폐기시키기 위해, 사용된 원자핵종-특이성 매질인 방사성 고체 폐기물을 형성하도록 노출시키고; 실질적으로 비-방사성 원자핵종인 사용된 재생제 용액을 방출시키고; 추가의 방사성 액체를 처리하기 위해 상기 재생된 이온 교환 수지를 재사용하는 단계를 특징으로 하는 방사성 액체를 처리하는 방법.Contacting the radioactive liquid containing the radionuclide and non-radioactive nuclide with an ion exchange resin to expose from the liquid to form a used ion exchange resin containing the radionuclide and non-radioactive nuclide; Regenerating the used ion exchange resin to release the radionuclide and non-radioactive nuclide contained in the used ion ion exchange resin into the regenerant solution used; The used regenerant solution comprising the radionuclide and non-radionuclide is contacted with a nuclide-specific medium to selectively separate and discard the radionuclide from the used regenerant solution and discard it. Exposing to form a radioactive solid waste that is a nuclide-specific medium; Releasing the used regenerant solution that is substantially non-radioactive nuclide; Recycling said regenerated ion exchange resin to treat further radioactive liquid. 제1항에 있어서, 상기 방사성 액체를 실질적으로 완전히 사용될 때까지 이온 교환 수지와 접촉하도록 노출시키는 방법.The method of claim 1 wherein the radioactive liquid is exposed to contact with the ion exchange resin until substantially fully used. 제1항에 있어서, 상기 사용된 재생제 용액을 실질적으로 완전히 사용될 때까지 원자핵종-특이성 매질과 접촉하도록 노출시키는 방법.The method of claim 1, wherein the used regenerant solution is exposed to contact with the nuclide-specific medium until substantially completely used. 제1항에 있어서, 상기 이온 교환수지가 유기 이온 교환 수지인 방법.The method of claim 1, wherein the ion exchange resin is an organic ion exchange resin. 제1항에 있어서, 상기 원자핵종-특이성 매질이, 상기 방사성 원자핵종이 고체 방사성 폐기물로서 고정되는 원자핵종-특이성 이온 교환 수지인 방법.The method of claim 1, wherein the nuclide-specific medium is an nuclide-specific ion exchange resin in which the radionuclide is immobilized as a solid radioactive waste. 제1항에 있어서, 상기 재생제가 치환가능한 양이온을 포함하는 방법.The method of claim 1 wherein said regenerant comprises a substitutable cation. 제1항에 있어서, 상기 재생제가 치환가능한 음이온을 포함하는 방법.The method of claim 1 wherein said regenerant comprises a substitutable anion. ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.※ Note: The disclosure is based on the initial application.
KR1019940018028A 1993-07-26 1994-07-26 Treatment method of radioactive liquid KR950004288A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US9623493A 1993-07-26 1993-07-26
US8/096,234 1993-07-26

Publications (1)

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KR950004288A true KR950004288A (en) 1995-02-17

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JP (1) JPH0777599A (en)
KR (1) KR950004288A (en)
FR (1) FR2708373A1 (en)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9714457B2 (en) * 2012-03-26 2017-07-25 Kurion, Inc. Submersible filters for use in separating radioactive isotopes from radioactive waste materials
JP6009218B2 (en) * 2011-05-24 2016-10-19 ローム アンド ハース エレクトロニック マテリアルズ エルエルシーＲｏｈｍ ａｎｄ Ｈａａｓ Ｅｌｅｃｔｒｏｎｉｃ Ｍａｔｅｒｉａｌｓ ＬＬＣ Alpha particle emitter removal
CN110467190B (en) * 2018-05-09 2024-04-09 上海核工程研究设计院股份有限公司 Device and method for recycling boron from radioactive boron-containing waste liquid

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JPS5122599B2 (en) * 1972-12-13 1976-07-10
US4087375A (en) * 1975-05-07 1978-05-02 Shin Tohoku Chemical Industry Co., Ltd. Method for treating radioactive waste water
JPS6262298A (en) * 1985-09-12 1987-03-18 三菱重工業株式会社 Method of processing radioactive ion exchange resin
JPS6262295A (en) * 1985-09-12 1987-03-18 三菱重工業株式会社 Method of processing radioactive ion exchange resin
JPH0664190B2 (en) * 1988-08-09 1994-08-22 東京電力株式会社 Radionuclide-containing waste liquid treatment method
US6165367A (en) * 1991-09-19 2000-12-26 Siemens Power Corporation Method for removing a heavy metal from a waste stream

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FR2708373A1 (en) 1995-02-03
JPH0777599A (en) 1995-03-20

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