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      KCI등재 SCIE SCOPUS

      POINTWISE CROSS-SECTION-BASED ON-THE-FLY RESONANCE INTERFERENCE TREATMENT WITH INTERMEDIATE RESONANCE APPROXIMATION

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      https://www.riss.kr/link?id=A104153642

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      다국어 초록 (Multilingual Abstract)

      The effective cross sections (XSs) in the direct whole core calculation code nTRACER are evaluated by the equivalence theory-based resonance-integral-table method using the WIMS-based library as an alternative to the subgroup method. The background XS...

      The effective cross sections (XSs) in the direct whole core calculation code nTRACER are evaluated by the equivalence theory-based resonance-integral-table method using the WIMS-based library as an alternative to the subgroup method. The background XSs, as well as the Dancoff correction factors, were evaluated by the enhanced neutron-current method. A method, with pointwise microscopic XSs on a union-lethargy grid, was used for the generation of resonance-interference factors (RIFs) for mixed resonant absorbers.
      This method was modified by the intermediate-resonance approximation by replacing the potential XSs for the non-absorbing moderator nuclides with the background XSs and neglecting the resonance-elastic scattering. The resonance-escape probability was implemented to incorporate the energy self-shielding effect in the spectrum. The XSs were improved using the proposed method as compared to the narrow resonance infinite massbased method. The RIFs were improved by 1% in 235U, 7% in 239Pu, and >2% in 240Pu. To account for thermal feedback, a new feature was incorporated with the interpolation of pre-generated RIFs at the multigroup level and the results compared with the conventional resonance-interference model. This method provided adequate results in terms of XSs and k-eff. The results were verified first by the comparison of RIFs with the exact RIFs, and then comparing the XSs with the McCARD calculations for the homogeneous configurations, with burned fuel containing a mixture of resonant nuclides at different burnups and temperatures. The RIFs and XSs for the mixture showed good agreement, which verified the accuracy of the RIF evaluation using the proposed method. The method was then verified by comparing the XSs for the virtual environment for reactor applicationbenchmark pin-cell problem, as well as the heterogeneous pin cell containing burned fuel with McCARD. The method works well for homogeneous, as well as heterogeneous configurations.

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      참고문헌 (Reference)

      1 F. Leszczynski, "WIMS Library Update"

      2 A. T. Godfrey, "VERA Core Physics Benchmark Progression Problem Specifications" CASL 2014

      3 Z. Gao, "The treatment of resonance interference effects in the subgroup method" 38 : 995-1103, 2011

      4 R. E. MacFarlane, "The NJOY Nuclear Data Processing System, Ver. 2012" Los Alamos National Laboratory 2012

      5 H.G. Joo, "Subgroup weight generation based on shielded pin-cell cross section conservation" 36 : 859-868, 2009

      6 S. Choi, "Resonance self-shielding method with resonance interference factor library" 2014

      7 Y.S. Jung, "Practical numerical reactor employing direct whole core neutron transport and sub-channel thermal/hydraulic solvers" 62 : 357-374, 2013

      8 R.J.J. Stammler, "Methods of Steady-state Reactor Physics in Nuclear Design" Academic Press 1983

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

      10 K. O. Ott, "Introductory Nuclear Reactor Statics, American Nuclear Society, 555 North Kensington Avenue"

      1 F. Leszczynski, "WIMS Library Update"

      2 A. T. Godfrey, "VERA Core Physics Benchmark Progression Problem Specifications" CASL 2014

      3 Z. Gao, "The treatment of resonance interference effects in the subgroup method" 38 : 995-1103, 2011

      4 R. E. MacFarlane, "The NJOY Nuclear Data Processing System, Ver. 2012" Los Alamos National Laboratory 2012

      5 H.G. Joo, "Subgroup weight generation based on shielded pin-cell cross section conservation" 36 : 859-868, 2009

      6 S. Choi, "Resonance self-shielding method with resonance interference factor library" 2014

      7 Y.S. Jung, "Practical numerical reactor employing direct whole core neutron transport and sub-channel thermal/hydraulic solvers" 62 : 357-374, 2013

      8 R.J.J. Stammler, "Methods of Steady-state Reactor Physics in Nuclear Design" Academic Press 1983

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

      10 K. O. Ott, "Introductory Nuclear Reactor Statics, American Nuclear Society, 555 North Kensington Avenue"

      11 D.G. Cacuci, "Handbook of Nuclear Engineering" Springer 2010

      12 A. Yamamoto, "Evaluation of background cross sections for heterogeneous and complicated geometry by the enhanced neutron current method" 45 : 1287-1292, 2008

      13 M.B. Chadwick, "ENDF/B-VII.0: next generation evaluated nuclear data library for Nuclear Science and Technology" 107 : 2931-3060, 2006

      14 M.L. Williams, "Correction of multigroup cross sections for resolved resonance interference in mixed absorbers" 83 : 73-49, 1983

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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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