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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
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초록· 키워드
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Background: The current status of ACE format MCNP/MCNPX libraries by NDC of KAERI is presented with a short description of each library. Materials and Methods: Validation calculations with recent nuclear data evaluations ENDF/BV-II. 0, ENDF/B-VII.1, JEFF-3.2, and JENDL-4.0 have been carried out by the MCNP5 code for 119 criticality benchmark problems taken from the expanded criticality validation suite supplied by LANL. The overall performances of the ACE format KN-libraries have been analyzed in comparison with the results calculated with the ENDF/B-VII.0-based ENDF70 library of LANL. Results and Discussion: It was confirmed that the ENDF/B-VII.1-based KNE71 library showed better performances than the others by comparing the RMS errors and ${chi}^2$ values for five benchmark categories as well as whole benchmark problems. ENDF/B-VII.1 and JEFF-3.2 have a tendency to yield more reliable MCNP calculation results within certain confidence intervals regarding the total uncertainties for the $k_{eff}$ values. Conclusion: It is found that the adoption of the latest evaluated nuclear data might ensure better outcomes in various research and development areas.
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참고문헌 (5)
참고문헌 신청
Conlin JL / 2013 / Continuous energy neutron cross section data tables based upon ENDF/B-VII.1 :1~2
Mosteller RD / 2010 / An expanded criticality validation suite for MCNP :1~226
Trellue HR / 2009 / ENDF70: A continuous-energy MCNP neutron data library based on ENDF/B-VII.0 / Nucl. Technol 168:832~836
MacFarlane RE / 2012 / The NJOY nuclear data processing system, version 2012 :493~544
Kim DH / 2003 / Comparisons of the MCNP criticality benchmark suite with ENDF/B-VI.8, JENDL-3.3, and JEFF-3.0. ICNC2003 / Seventh International Conference on Nuclear Criticality Safety :20~244444
Mosteller RD / 2010 / An expanded criticality validation suite for MCNP :1~226
Trellue HR / 2009 / ENDF70: A continuous-energy MCNP neutron data library based on ENDF/B-VII.0 / Nucl. Technol 168:832~836
MacFarlane RE / 2012 / The NJOY nuclear data processing system, version 2012 :493~544
Kim DH / 2003 / Comparisons of the MCNP criticality benchmark suite with ENDF/B-VI.8, JENDL-3.3, and JEFF-3.0. ICNC2003 / Seventh International Conference on Nuclear Criticality Safety :20~244444
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