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      KCI등재 SCOPUS

      심부시추공 처분용기 재료로서 SiC 세라믹의 적합성 평가 = Evaluation of Silicon Carbide (SiC) for Deep Borehole Disposal Canister

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      https://www.riss.kr/link?id=A105515453

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      다국어 초록 (Multilingual Abstract)

      To overcome the low mechanical strength and corrosion behavior of a carbon steel canister at high temperature condition of a deep borehole, SiC ceramics were studied as an alternative material for the disposal canister. In this paper, a design concept...

      To overcome the low mechanical strength and corrosion behavior of a carbon steel canister at high temperature condition of a deep borehole, SiC ceramics were studied as an alternative material for the disposal canister. In this paper, a design concept for a SiC canister, along with an outer stainless steel container, was proposed, and its manufacturing feasibility was tested by fabricating several 1/3 scale canisters. The proposed canister can contain one PWR assembly. The outer container was also prepared for the string formation of SiC canisters. Thermal conductivity was measured for the SiC canister. The canister had a good thermal conductivity of above $70W{\cdot}m^{-1}{\cdot}K^{-1}$ at $100^{\circ}C$. The structural stability was checked under KURT environment, and it was found that the SiC ceramics did not exhibit any change for the 3 year corrosion test at $70^{\circ}C$. Therefore, it was concluded that SiC ceramics could be a good alternative to carbon steel in application to deep borehole disposal canisters.

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      참고문헌 (Reference)

      1 B. Kursten, "State-of-the-art document on the Corrosion Behaviour of Container Materials, European Commission 5th Euratom Framework Programnne 1998-2002 Final Report, Contract No FIKW-CT-20014-20138" 2002

      2 K.S. Kim, "State-of-the Art Report on the Very Deep Borehole Disposal Concept for High-level Radioactive Waste, Korea Atomic Energy Research Institute Report, KAERI/AR-929/2012" 2012

      3 B W. Arnold, "Reference Design and Operations for Deep Borehole Disposal of High-Level Radioactive Waste, Sandia Report, SAND2011-6749" 2011

      4 J. Outinen, "Mechanical Properties of Structural Steel at Elevated Temperatures and After Cooling" 273-289, 2002

      5 J.Y. Lee, "Key Factors to Determine the Borehole Spacing in a Deep Borehole Disposal for HLW" 47 (47): 1-, 2015

      6 B. Arnold, "Geological and Practical Aspects of Deep Borehole Disposal, Sandia Report, SAND2012-138" 2012

      7 G.N. Vigilante, "Elevated Temperature Properties of Steels, Technical Report ARCCB-TR-96023" US Army Armament Research, Development and Engineering Center 1996

      8 P.V. Brady, "Deep Borehole Disposal of High-Level Radioactive Waste, Sandia Report, SAND2009-4401" 2009

      9 Nuclear Industry Radioactive Waste Executive, "A Review of the Deep Borehole Disposal Concept for Radioactive Waset" Nirex 2004

      1 B. Kursten, "State-of-the-art document on the Corrosion Behaviour of Container Materials, European Commission 5th Euratom Framework Programnne 1998-2002 Final Report, Contract No FIKW-CT-20014-20138" 2002

      2 K.S. Kim, "State-of-the Art Report on the Very Deep Borehole Disposal Concept for High-level Radioactive Waste, Korea Atomic Energy Research Institute Report, KAERI/AR-929/2012" 2012

      3 B W. Arnold, "Reference Design and Operations for Deep Borehole Disposal of High-Level Radioactive Waste, Sandia Report, SAND2011-6749" 2011

      4 J. Outinen, "Mechanical Properties of Structural Steel at Elevated Temperatures and After Cooling" 273-289, 2002

      5 J.Y. Lee, "Key Factors to Determine the Borehole Spacing in a Deep Borehole Disposal for HLW" 47 (47): 1-, 2015

      6 B. Arnold, "Geological and Practical Aspects of Deep Borehole Disposal, Sandia Report, SAND2012-138" 2012

      7 G.N. Vigilante, "Elevated Temperature Properties of Steels, Technical Report ARCCB-TR-96023" US Army Armament Research, Development and Engineering Center 1996

      8 P.V. Brady, "Deep Borehole Disposal of High-Level Radioactive Waste, Sandia Report, SAND2009-4401" 2009

      9 Nuclear Industry Radioactive Waste Executive, "A Review of the Deep Borehole Disposal Concept for Radioactive Waset" Nirex 2004

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2024 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2021-07-28 학술지명변경 한글명 : 방사성폐기물학회지 -> Journal of Nuclear Fuel Cycle and Waste Technology KCI등재
      2021-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2020-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2017-01-01 평가 등재학술지 유지 (계속평가) KCI등재
      2014-08-07 학술지명변경 외국어명 : Journal of Nuclear Fuel Cycle and Waste Technology (Korean) -> Journal of Nuclear Fuel Cycle and Waste Technology KCI등재
      2013-11-26 학술지명변경 외국어명 : Journal of the Korean Radioactive Waste Society -> Journal of Nuclear Fuel Cycle and Waste Technology (Korean) KCI등재
      2013-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2010-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      2009-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2008-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      2006-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.17 0.17 0.17
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.15 0.16 0.409 0.08
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