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      KCI등재 SCIE SCOPUS

      One-step Monte Carlo Global Homogenization Based on RMC code

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      https://www.riss.kr/link?id=A106280115

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      다국어 초록 (Multilingual Abstract)

      Due to the limitation of the computers, the conventional homogenization method is based on manyassumptions and approximations, and some tough problems such as energy spectrum and boundarycondition are faced. To deal with those problems, the Monte Carl...

      Due to the limitation of the computers, the conventional homogenization method is based on manyassumptions and approximations, and some tough problems such as energy spectrum and boundarycondition are faced. To deal with those problems, the Monte Carlo global homogenization is adopted. TheReactor Monte Carlo code RMC is used to study the global homogenization method, and the one-stepglobal homogenization method is proposed. The superimposed mesh geometry is also used to dividethe physical models, leading to better geometric flexibility. A set of multigroup homogenization crosssections is online generated for each mesh under the real neutron energy spectrum and boundarycondition, the cross sections are adjusted by the superhomogenization method, and no leakagecorrection is required. During the process of superhomogenization, the author-developed reactor coreprogram NLSP3 is used for global calculation, so the global flux distribution and equivalent homogenizationcross sections could be solved simultaneously. Meanwhile, the calculated homogenization crosssection could accurately reconstruct the non-homogenization flux distribution and could also be used forfine calculation. This one-step global homogenization method was tested by a PWR assembly and a smallreactor model, and the results show the validity.

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      참고문헌 (Reference)

      1 Q. Q. Pan, "The optimal source bias method based on RMC code" 121 : 525-530, 2018

      2 J.S. Hendricks, "Superimposed Mesh Plotting in MCNP. LA-UR-01-1003"

      3 P. Zhang, "Research on the Reactor Physics Analysis Methods and Characteristics of Supercritical Water-Cooled reactor" Tsinghua University 2012

      4 M. C. Li, "Research on Lattice Homogenization via Continuous-Energy Monte Carlo Method" Tsinghua University 2012

      5 W. Boyd, "Reactor multi-group cross sction generation for fine-mesh deterministic neutron transport simulations" Institute of Technology 2017

      6 K. Wang, "RMC - a Monte Carlo code for reactor core analysis" 82 : 121-129, 2015

      7 J. Leppanen, "Overview of the methodology for spatial homogenization in the Serpent 2 Monte Carlo code" 96 : 126-136, 2016

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

      9 A. Yamamoto, "Improvement of SPH method for pin-by-pin core calculations" 41 (41): 1155-1165, 2004

      10 J. H. Won, "Discrete ordinates method-like transport computation with equivalent group condensation and angle-collapsing for local/global iteration" 38 (38): 846-852, 2011

      1 Q. Q. Pan, "The optimal source bias method based on RMC code" 121 : 525-530, 2018

      2 J.S. Hendricks, "Superimposed Mesh Plotting in MCNP. LA-UR-01-1003"

      3 P. Zhang, "Research on the Reactor Physics Analysis Methods and Characteristics of Supercritical Water-Cooled reactor" Tsinghua University 2012

      4 M. C. Li, "Research on Lattice Homogenization via Continuous-Energy Monte Carlo Method" Tsinghua University 2012

      5 W. Boyd, "Reactor multi-group cross sction generation for fine-mesh deterministic neutron transport simulations" Institute of Technology 2017

      6 K. Wang, "RMC - a Monte Carlo code for reactor core analysis" 82 : 121-129, 2015

      7 J. Leppanen, "Overview of the methodology for spatial homogenization in the Serpent 2 Monte Carlo code" 96 : 126-136, 2016

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

      9 A. Yamamoto, "Improvement of SPH method for pin-by-pin core calculations" 41 (41): 1155-1165, 2004

      10 J. H. Won, "Discrete ordinates method-like transport computation with equivalent group condensation and angle-collapsing for local/global iteration" 38 (38): 846-852, 2011

      11 I. Petrovic, "BN Theory: Advances and New Models for Neutron Leakage Calculation" Plenum Press 223-281, 1996

      12 S. Liu, "BEAVRS full core burnup calculation in hot full power condition by RMC code" 101 : 434-446, 2017

      13 T. Hideki, "Accuracy of interpolation methods for resonance selfshielding factors" 18 (18): 152-161, 1981

      14 Q.Q. Pan, "A new nonlinear iterative method for SPN theory" 110C : 920-927, 2017

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      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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