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      KCI등재 SCIE SCOPUS

      A New Approach to Determine Batch Size for the Batch Method in the Monte Carlo Eigenvalue Calculation

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      https://www.riss.kr/link?id=A106246360

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      다국어 초록 (Multilingual Abstract)

      It is well known that the variance of tally is biased in a Monte Carlo calculation based on the poweriteration method. Several studies have been conducted to estimate the real variance. Among them, thebatch method, which was proposed by Gelbard and Pr...

      It is well known that the variance of tally is biased in a Monte Carlo calculation based on the poweriteration method. Several studies have been conducted to estimate the real variance. Among them, thebatch method, which was proposed by Gelbard and Prael, has been utilized actively in many Monte Carlocodes because the method is straightforward, and it is easy to implement the method in the codes.
      However, there is a problem when utilizing the batch method because the estimated variance variesdepending on batch size. Often, the appropriate batch size is not realized before the completion ofseveral Monte Carlo calculations. This study recognizes this shortcoming and addresses it by permittingselection of an appropriate batch size

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      참고문헌 (Reference)

      1 Hyung Jin Shim, "Real Variance Estimation Using an Intercycle Fission Source Correlation for Monte Carlo Eigenvalue Calculations" Informa UK Limited 162 (162): 98-108, 2017

      2 C.M. Perfetti, "Quantifying the effect of undersampling in Monte Carlo simulations using scale" 2014

      3 T.Y. Yamamoto, "OECD/NEA Source Convergence Benchmark 3 : Three Thick One-Dimensional Slabs"

      4 D. Rochman, "Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation" Elsevier BV 92 : 150-160, 2016

      5 A. Haghighat, "Monte Carlo Methods for Particle Transport" CRC Press 2015

      6 심형진, "MCCARD: MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS" 한국원자력학회 44 (44): 161-176, 2012

      7 MATLAB, "MATLAB and Statistics Toolbox Release"

      8 L. M. Petrie, "KENO IV an Imporoved Monte Carlo Criticality Program" 1975

      9 N. Z. Cho, "Development of VHTR Core Analysis and Verification Methodology" Korea Atomic Energy Research Institute 2006

      10 E.M. Gelbard, "Computation of standard deviations in Eigenvalue calculations" Elsevier BV 24 (24): 237-241, 1990

      1 Hyung Jin Shim, "Real Variance Estimation Using an Intercycle Fission Source Correlation for Monte Carlo Eigenvalue Calculations" Informa UK Limited 162 (162): 98-108, 2017

      2 C.M. Perfetti, "Quantifying the effect of undersampling in Monte Carlo simulations using scale" 2014

      3 T.Y. Yamamoto, "OECD/NEA Source Convergence Benchmark 3 : Three Thick One-Dimensional Slabs"

      4 D. Rochman, "Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation" Elsevier BV 92 : 150-160, 2016

      5 A. Haghighat, "Monte Carlo Methods for Particle Transport" CRC Press 2015

      6 심형진, "MCCARD: MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS" 한국원자력학회 44 (44): 161-176, 2012

      7 MATLAB, "MATLAB and Statistics Toolbox Release"

      8 L. M. Petrie, "KENO IV an Imporoved Monte Carlo Criticality Program" 1975

      9 N. Z. Cho, "Development of VHTR Core Analysis and Verification Methodology" Korea Atomic Energy Research Institute 2006

      10 E.M. Gelbard, "Computation of standard deviations in Eigenvalue calculations" Elsevier BV 24 (24): 237-241, 1990

      11 N. Horelik, "Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS)"

      12 J. Miao, "Analysis of correlations and their impact on convergence rates in Monte Carlo eigenvalue simulations" Elsevier BV 92 : 81-95, 2016

      13 Song Hyun Kim, "A batch size selection strategy by checking stability of fission source distribution for Monte Carlo eigenvalue calculations" Informa UK Limited 54 (54): 301-311, 2016

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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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