KR870700248A - Radioactive waste treatment method and treatment device - Google Patents

Radioactive waste treatment method and treatment device

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Publication number
KR870700248A
KR870700248A KR860700206A KR860700206A KR870700248A KR 870700248 A KR870700248 A KR 870700248A KR 860700206 A KR860700206 A KR 860700206A KR 860700206 A KR860700206 A KR 860700206A KR 870700248 A KR870700248 A KR 870700248A
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South Korea
Prior art keywords
radioactive waste
degassing
treating
solidifying
gas
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KR860700206A
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Korean (ko)
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기요미 후나바시
마사미 마쓰다
히데오 유사
가즈히데 모리
마꼬도 기꾸찌
Original Assignee
미다 가쓰시게
가부시기가이샤 히다찌 세이사꾸쇼
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Publication of KR870700248A publication Critical patent/KR870700248A/en

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/32Processing by incineration

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  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)
  • Separation, Recovery Or Treatment Of Waste Materials Containing Plastics (AREA)
  • Excavating Of Shafts Or Tunnels (AREA)
  • Fertilizers (AREA)

Abstract

내용 없음No content

Description

방사성 폐기물의 처리방법 및 처리장치Radioactive waste treatment method and treatment device

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

제1도는 본원 발명을 실시하는데 효과적인 열분해 고화시스템의 계통도이다.1 is a schematic diagram of a pyrolysis solidification system effective for practicing the present invention.

Claims (21)

주로 사용이 끝난 이온교환수지로 이루어진 방사성 폐기물의 처리방법에 있어서, 상기 방사성 폐기물을 가열하여, 상기 사용이 끝난 이온교환수지의 이온교환기를 열분해하고, 상기 방사성 폐기물을 탄소화한 다음, 상기 방사성 폐기물에 흡착되어 있는 기체를 탈기(脫氣)시키며, 그 후 상기 방사성 폐기물을 고화(固化)하는 것을 특징으로 하는 방사성 폐기물의 폐리방법.In the method of treating a radioactive waste consisting mainly of used ion exchange resin, the radioactive waste is heated, pyrolysing the ion exchanger of the used ion exchange resin, carbonizing the radioactive waste, and then radioactive waste. And degassing the gas adsorbed on the substrate, and then solidifying the radioactive waste. 제1항에 있어서, 상기 열분해는 불활성가스중에서 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.The radioactive waste treatment method according to claim 1, wherein the pyrolysis is performed in an inert gas. 제1항에 있어서, 상기 탈기는 상기 방사성 폐기물을 액체중에 담그어서 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.The method for treating radioactive waste according to claim 1, wherein the degassing is performed by dipping the radioactive waste in a liquid. 제3항에 있어서, 상기 액체는 물임을 특징으로 하는 방사성 폐기물의 처리방법.4. The method of claim 3, wherein the liquid is water. 제4항에 있어서, 상기 고화는 상기 방사성 폐기물고 상기 물과 수경성 고화제인 시멘트를 혼합함으로써 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.The radioactive waste treatment method according to claim 4, wherein the solidification is performed by mixing the radioactive waste and cement which is the water and the hydraulic solidifying agent. 제4항에 있어서, 상기 고화는 상기 방사성 폐기물과 상기 물과 규산알칼리분말과 경화제를 혼합합으로써 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.The radioactive waste treatment method according to claim 4, wherein the solidification is performed by mixing the radioactive waste, the water, an alkali silicate powder, and a curing agent. 제3항에 있어서, 상기 액체는 규산알칼리용액임을 특징으로 하는 방사성 폐기물의 처리방법.The method of claim 3, wherein the liquid is an alkali silicate solution. 제7항에 있어서, 상기 고화는 상기 방사성 폐기물과 상기 규산알칼리용액과 경화제를 혼함함으로써 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.8. The method for treating radioactive waste according to claim 7, wherein the solidification is performed by mixing the radioactive waste, the alkali silicate solution and a curing agent. 제1항에 있어서, 상기 탈기는 상기 방사성 폐기물을 진공용 하우징내에 도입하고, 상기 진공용 하우징내를 진공 흡인하여 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.The method for treating radioactive waste according to claim 1, wherein the degassing is performed by introducing the radioactive waste into a vacuum housing and vacuum sucking the inside of the vacuum housing. 제9항에 있어서, 상기 고화는 상기 방사성 페기물과 물과 수경성 고화제인 시멘트를 혼합함으로써 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.10. The method for treating radioactive waste according to claim 9, wherein the solidification is performed by mixing the radioactive waste, water and cement which is a hydraulic hardener. 제9항에 있어서, 상기 고화는 상기 방사성 폐기물과 규산알칼리용액과 경화제를 혼합함으로써 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.The method for treating radioactive waste according to claim 9, wherein the solidification is performed by mixing the radioactive waste, an alkali silicate solution, and a curing agent. 제9항에 있어서, 상기 고화는 상기 방사성 폐기물과 규산알칼리분말과 경화제와 물을 혼합함으로써 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.10. The method for treating radioactive waste according to claim 9, wherein the solidification is performed by mixing the radioactive waste, alkali silicate powder, a curing agent, and water. 제8항에 있어서, 상기 경화제는 롤리인산규소, 알칼리토류금속염, 무기인산으로 구성되는 기(基)에서 선택하는 것을 특징으로 하는 방사성 폐기물의 처리방법.9. The method of claim 8, wherein the curing agent is selected from a group consisting of silicon rolyphosphate, alkaline earth metal salts, and inorganic phosphoric acid. 주로 사용이 끝난 이온교환수지로 이루어진 방사성 폐기물의 처리방법에 있어서, 상기 방사성 폐기물을 가열하여, 상기 사용이 끝난 이온교환수지의 이온교환기를 열분해하고, 상기 방사성 폐기물을 탄소화 한 다음, 상기 방사성 폐기물을 펠렛화하고, 이것을 일정기간 저장하여 방사능을 감쇠시키는 것을 특징으로하는 방사성 폐기물의 처리방법.In the method of treating a radioactive waste consisting mainly of used ion exchange resin, the radioactive waste is heated, pyrolysing the ion exchanger of the used ion exchange resin, carbonizing the radioactive waste, and then the radioactive waste. Pelletizing and storing for a certain period of time to attenuate radioactivity, characterized in that the radioactive waste treatment method. 제14항에 있어서, 상기 열분해는 불활성가스중에서 행하는 것을 특징으로 하는 방사성 폐기물의 처리방법.The radioactive waste treatment method according to claim 14, wherein the pyrolysis is performed in an inert gas. 주로 사용이 끝난 이온교환수지로 이루어진 방사성 폐기물의 처리장치에 있어서, 상기 방사성 폐기물을 가열하여 탄소화하는 열분해장치와, 상기 열분해 장치내에서 발생하는 가스를 열분해장치밖으로 배출해서 이 가스를 처리하는 배기가스처리장치와, 탄소화된 상기 방사성 폐기물에 흡착되어 있는 기체를 탈기하기 위한 탈기수단과, 탈기후의 상기 방사성 폐기물을 고화하는 고화수단으로 이루어지는 것을 특징으로 하는 방사성 폐기물의 처리장치.A radioactive waste treatment apparatus consisting mainly of ion-exchange resins, comprising: a pyrolysis apparatus for heating and carbonizing the radioactive waste, and an exhaust gas for treating the gas by discharging the gas generated in the pyrolysis apparatus out of the pyrolysis apparatus. And a degassing means for degassing gas adsorbed to the carbonized radioactive waste, and a solidifying means for solidifying the radioactive waste after degassing. 제16항에 있어서, 상기 열분해장치는 이 장치내에 불활성 가스를 공급하는 불활성가스공급장치를 갖는 것을 특징으로 하는 방사성 폐기물의 처리장치.The radioactive waste treatment apparatus according to claim 16, wherein the pyrolysis apparatus has an inert gas supply apparatus for supplying an inert gas into the apparatus. 제16항에 있어서, 상기 탈기수단은 탈기하기 위한 액체를 채우는 용기를 갖고 있는 것을 특징으로 하는 방사성 폐기물의 처리장치.The radioactive waste treatment apparatus according to claim 16, wherein the degassing means has a container for filling liquid for degassing. 제16항에 있어서, 상기 탈기수단은 진공 탈기하기 위한 진공용 하우징을 갖는 것을 특징으로 하는 방사성 페기물의 처리장치.17. The apparatus of claim 16, wherein the degassing means has a vacuum housing for vacuum degassing. 제16항에 있어서, 상기 탈기수단은 이 수단에 상기 방사성 폐기물을 담그기 위한 고화제 용액을 공급하는 고화제 공급장치를 가지며, 상기 고화수단은 이 수단에 상기 방사성 폐기물을 고화하기 위한 고화제를 공급하는 화제공급장치를 갖는 것을 특징으로 하는 방사성 폐기물의 처리장치.17. The degassing means according to claim 16, wherein the degassing means has a solidifying agent supplying device for supplying a solidifying solution for dipping the radioactive waste into the means, wherein the solidifying means supplies a solidifying agent for solidifying the radioactive waste to the means. Apparatus for treating radioactive waste, characterized in that it has a topical supply device. 주로 사용이 끝난 이온교환수지로 이루어진 방사성 폐기물의 처리장치에 있어서, 상기 방사성 폐기물을 가열하여 탄소화하는 열분해 장치와 상기 열분해장치내에서 발생하는 가스를 상기 열분해장치 밖으로 배출하여 상기 가스를 처리하는 배기가스 처리장치와, 탄소화된 상기 방사성 폐기물을 펠렛화하기 위한 조립기(造粒器)와, 펠렛화된 상기 방사성 폐기물에 흡착되어 있는 기체를 탈기시키는 탈기수단과, 탈기 후의 펠렛화된 방사성 폐기물을 고화하는 고화수단으로 이루어지는 것을 특징으로 하는 방사성 폐기물의 처리장치.In the radioactive waste treatment apparatus mainly consisting of the used ion exchange resin, a pyrolysis apparatus for heating and carbonizing the radioactive waste and an exhaust gas for discharging the gas generated in the pyrolysis apparatus out of the pyrolysis apparatus to treat the gas. A gas treatment apparatus, a granulator for pelletizing the carbonized radioactive waste, degassing means for degassing gas adsorbed to the pelletized radioactive waste, and pelletized radioactive waste after degassing An apparatus for treating radioactive waste, characterized by comprising a solidifying means for solidifying. ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.※ Note: The disclosure is based on the initial application.
KR860700206A 1984-08-31 1985-08-28 Radioactive waste treatment method and treatment device KR870700248A (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
JP59180561A JPS6159299A (en) 1984-08-31 1984-08-31 Method and device for treating radioactive waste
JP84-180561 1984-08-31
PCT/JP1985/000472 WO1986001633A1 (en) 1984-08-31 1985-08-28 Method of and apparatus for treating radioactive waste

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KR870700248A true KR870700248A (en) 1987-05-30

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DE (1) DE3579312D1 (en)
WO (1) WO1986001633A1 (en)

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JP4322735B2 (en) * 2004-05-27 2009-09-02 株式会社東芝 Method and apparatus for solidifying radioactive waste
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CN103219059B (en) * 2013-04-10 2016-04-20 中广核工程有限公司 Radioactive spent resin metering system
CN104064239B (en) * 2014-07-14 2018-05-29 中广核工程有限公司 A kind of low middle Intermediate Level Radioactive activated carbon processing method of nuclear power station
KR101776905B1 (en) 2017-06-09 2017-09-08 (주)한국원자력 엔지니어링 Consolidation Method and Apparatus of Carbonization By-product Producted by Middle and Low level Radiative Waste Carbonization System

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JPS6159299A (en) 1986-03-26
JPH0448199B2 (en) 1992-08-06
EP0192777B1 (en) 1990-08-22
EP0192777A1 (en) 1986-09-03
EP0192777A4 (en) 1986-10-02
DE3579312D1 (en) 1990-09-27
WO1986001633A1 (en) 1986-03-13

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