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      금속연료 소듐냉각고속로 중대사고 고유안전특성 SAS4A/SASSYS-1 코드 전산해석

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      https://www.riss.kr/link?id=A107338925

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      다국어 초록 (Multilingual Abstract) kakao i 다국어 번역

      The inherent safety characteristics of the metal fuel core sodium-cooled fast reactor (SFR) are investigated using the SAS4A metal fuel version code, originally developed for the analysis of postulated severe accidents in oxide fuel SFR and significantly extended to allow the mechanistic analysis of severe accidents in metallic fuel SFRs. The paper provides an overview of the SAS4A key metal fuel models and the safety characteristics of the metal fuels. The analysis is performed for a postulated unprotected fuel assembly inlet blockage accident in the metal fuel Prototype Gen-IV Sodium Fast Reactor (PGSFR). The evolution of local fuel components during the pre-transient irradiation, molten fuel relocation behavior inside and outside of cladding, and their impacts on reactivity and power history during the transient are numerically analyzed. The favorable characteristics of the metal fuel, significant decreases in reactivity and power due to favorable molten fuel relocation and the fuel thermo-physical property change, are analyzed in the results.
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      The inherent safety characteristics of the metal fuel core sodium-cooled fast reactor (SFR) are investigated using the SAS4A metal fuel version code, originally developed for the analysis of postulated severe accidents in oxide fuel SFR and significan...

      The inherent safety characteristics of the metal fuel core sodium-cooled fast reactor (SFR) are investigated using the SAS4A metal fuel version code, originally developed for the analysis of postulated severe accidents in oxide fuel SFR and significantly extended to allow the mechanistic analysis of severe accidents in metallic fuel SFRs. The paper provides an overview of the SAS4A key metal fuel models and the safety characteristics of the metal fuels. The analysis is performed for a postulated unprotected fuel assembly inlet blockage accident in the metal fuel Prototype Gen-IV Sodium Fast Reactor (PGSFR). The evolution of local fuel components during the pre-transient irradiation, molten fuel relocation behavior inside and outside of cladding, and their impacts on reactivity and power history during the transient are numerically analyzed. The favorable characteristics of the metal fuel, significant decreases in reactivity and power due to favorable molten fuel relocation and the fuel thermo-physical property change, are analyzed in the results.

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      참고문헌 (Reference)

      1 강석훈, "수중폭발 이론을 사용한 노심폭주사고 시 노심 팽창 및 에너지 거동 수치해석" 한국전산유체공학회 21 (21): 8-14, 2016

      2 Sumer, T., "Unprotected Transient Analysis"

      3 Fanning, T.H, "The SAS4A/SASSYS-1Safety analysis code system, Version 5"

      4 Fistedis, S.H, "The Experimental Breeder Reactor-II Inherent Safety Demonstration" 101 : 1987

      5 Karahan, A., "SSCOMP-A: A Mechanistic Pre-Transient Characterization Model for Metallic Fuel Pins"

      6 Tentner, A., "PINACLE-M: The metal-fuel in-pin pre-failure molten fuel relocation module of the SAS4A code"

      7 Sumner, T, "PGSFR Safety Analysis for Protected Plant Transients"

      8 Tentner, A., "Overview of the SAS4A metallic fuel models and extended analysis of a postulated severe accident in the Prototype Gen-IV Sodium-Cooled Fast Reactor" 206 : 2020

      9 유재운, "Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea" 한국원자력학회 48 (48): 1059-1070, 2016

      10 Carmack, W.J, "Metal Fuels for advanced reactors" 392 : 2009

      1 강석훈, "수중폭발 이론을 사용한 노심폭주사고 시 노심 팽창 및 에너지 거동 수치해석" 한국전산유체공학회 21 (21): 8-14, 2016

      2 Sumer, T., "Unprotected Transient Analysis"

      3 Fanning, T.H, "The SAS4A/SASSYS-1Safety analysis code system, Version 5"

      4 Fistedis, S.H, "The Experimental Breeder Reactor-II Inherent Safety Demonstration" 101 : 1987

      5 Karahan, A., "SSCOMP-A: A Mechanistic Pre-Transient Characterization Model for Metallic Fuel Pins"

      6 Tentner, A., "PINACLE-M: The metal-fuel in-pin pre-failure molten fuel relocation module of the SAS4A code"

      7 Sumner, T, "PGSFR Safety Analysis for Protected Plant Transients"

      8 Tentner, A., "Overview of the SAS4A metallic fuel models and extended analysis of a postulated severe accident in the Prototype Gen-IV Sodium-Cooled Fast Reactor" 206 : 2020

      9 유재운, "Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea" 한국원자력학회 48 (48): 1059-1070, 2016

      10 Carmack, W.J, "Metal Fuels for advanced reactors" 392 : 2009

      11 Han, D.H., "KALIMER conceptual design report" KAERI 2002

      12 Sofu, T, "Implementation, verification and validation of the FPIN2 metal fuel pin mechanics model in the SASSYS/SAS4A LMR Transient analysis codes" 2 : 784-, 2012

      13 Kim, T.I., "Experimental studies on metallic fuel relocation in a single-pin core structure of a sodium-cooled fast reactor" 322 : 2017

      14 Bauer, T., "Behavior of modern metallic fuel in treat transient overpower tests" 92 : 1990

      15 Kim, T., "Analysis of Accident Scenarios for the Development of Probabilistic Safety Assessment Model for the Metallic Fuel Sodium-Cooled Fast Reactor" KAERI 2009

      16 TANJU SOFU, "A REVIEW OF INHERENT SAFETY CHARACTERISTICS OF METAL ALLOY SODIUM-COOLED FAST REACTOR FUEL AGAINST POSTULATED ACCIDENTS" 한국원자력학회 47 (47): 227-239, 2015

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2027 평가예정 재인증평가 신청대상 (재인증)
      2021-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2018-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2015-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2011-01-01 평가 등재 1차 FAIL (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      2005-06-16 학술지명변경 외국어명 : Jpurnal of Computatuonal Fluids Engineering -> Korean Society of Computatuonal Fluids Engineering KCI등재후보
      2005-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2004-01-01 평가 등재후보 1차 FAIL (등재후보1차) KCI등재후보
      2002-07-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.2 0.2 0.19
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.16 0.15 0.405 0.05
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