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      KCI등재 SCIE SCOPUS

      Design of large-scale sodium thermal-hydraulic integral effect test facility, STELLA-2

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      https://www.riss.kr/link?id=A108236375

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      다국어 초록 (Multilingual Abstract)

      The STELLA program was launched to support the PGSFR development in 2012 and for the 2nd stage, the STELLA-2 facility was designed to investigate the integral effect of safety systems including the comprehensive interaction among PHTS, IHTS and DHRS. ...

      The STELLA program was launched to support the PGSFR development in 2012 and for the 2nd stage, the STELLA-2 facility was designed to investigate the integral effect of safety systems including the comprehensive interaction among PHTS, IHTS and DHRS. In STELLA-2, the long-term transient behavior after accidents can be observed and the overall safety aspect can also be evaluated. In this paper, the basic design concept from engineering basis to specific design is described. The design was aimed to meet similarity criteria and requirements based on various non-dimensional numbers and the result satisfied the key features to explain the reasoning of safety evaluation. The result of this study was used to construct the facility and the experiment is on-going. In general, the final design meets the similarity criteria of the multidimensional physics inside the reactor pool. And also, for the conservation of natural circulation phenomena, the design meets the similarity requirements of geometry and thermo-dynamic behavior

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      참고문헌 (Reference)

      1 M. Ishii, "imilarity Analysis and Scaling Criteria for LWRs under Single-phase and Two-phase Natural Circulation" 1983

      2 C. Song, "Test Requirements for the Integral Effect Test to Simulate Korean PWR Plants" 2001

      3 M. Ishii, "Scientific Design of Purdue University Multi-Dimensional Integral Test Assembly (PUMA) for GE SBWR" 1996

      4 J. Hong, "Heat transfer performance test of PDHRS heat exchangers of PGSFR using STELLA-1 facility" 313 : 73-83, 2017

      5 윤정 ; 이제환 ; 김형모 ; 이용범 ; 어재혁, "Heat transfer characteristics of redan structure in large-scale test facility STELLA-2" 한국원자력학회 53 (53): 1109-1118, 2021

      6 M.P. Heisler, "Facility Requirements for Natural Convection Shutdown Removal System Testing"

      7 J. Lee, "Experimental study of sodium heat exchanger performance at high Pe number condition using STELLA-1 facility" 340 : 62-67, 2018

      8 Task Group on Advanced Reactor Experimental Facilities, "Experimental Facilities for Sodium Fast Reactor Safety Studies, vol. 12" OECD/NEA 2010-, 2010

      9 M. P. Heisler, "Development of scaling requirements for natural convection liquid-metal fast breeder reactor shutdown heat removal test facilities" 80 : 347-359, 1982

      10 J. Lee, "Design of electric core simulator system(ECSS)for large-scale integral effect test facility" 133 : 762-776, 2019

      1 M. Ishii, "imilarity Analysis and Scaling Criteria for LWRs under Single-phase and Two-phase Natural Circulation" 1983

      2 C. Song, "Test Requirements for the Integral Effect Test to Simulate Korean PWR Plants" 2001

      3 M. Ishii, "Scientific Design of Purdue University Multi-Dimensional Integral Test Assembly (PUMA) for GE SBWR" 1996

      4 J. Hong, "Heat transfer performance test of PDHRS heat exchangers of PGSFR using STELLA-1 facility" 313 : 73-83, 2017

      5 윤정 ; 이제환 ; 김형모 ; 이용범 ; 어재혁, "Heat transfer characteristics of redan structure in large-scale test facility STELLA-2" 한국원자력학회 53 (53): 1109-1118, 2021

      6 M.P. Heisler, "Facility Requirements for Natural Convection Shutdown Removal System Testing"

      7 J. Lee, "Experimental study of sodium heat exchanger performance at high Pe number condition using STELLA-1 facility" 340 : 62-67, 2018

      8 Task Group on Advanced Reactor Experimental Facilities, "Experimental Facilities for Sodium Fast Reactor Safety Studies, vol. 12" OECD/NEA 2010-, 2010

      9 M. P. Heisler, "Development of scaling requirements for natural convection liquid-metal fast breeder reactor shutdown heat removal test facilities" 80 : 347-359, 1982

      10 J. Lee, "Design of electric core simulator system(ECSS)for large-scale integral effect test facility" 133 : 762-776, 2019

      11 J. Lee, "Design evaluation of large-scale sodium integral effect test facility(STELLA-2)using MARS-LMR" 120 : 845-856, 2018

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      공동연구자 (7)

      유사연구자 (20) 활용도상위20명

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2023 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2020-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2014-01-01 평가 SCIE 등재 (등재유지) KCI등재
      2014-01-01 평가 SCOPUS 등재 (등재유지) KCI등재
      2011-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2007-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-07-31 학술지명변경 한글명 : Jorunal of the Korean Nuclear Society -> Nuclear Engineering and Technology
      외국어명 : 미등록 -> Nuclear Engineering and Technology
      KCI등재후보
      2004-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      2003-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2002-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      1999-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 1.04 0.17 0.77
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.63 0.56 0.343 0.11
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