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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.8
- 수록면
- 2,445 - 2,453 (9page)
- DOI
- https://doi.org/10.1016/j.net.2021.02.012
이용수
초록· 키워드
오류제보하기
Since the nuclear data forms a vital component in reactor physics computations, the nuclear communityneeds processing codes as tools for translating the Evaluated Nuclear Data Files (ENDF) to simulatenuclear-related problems such as an ACE format that is used for MCNP. Errors, inaccuracies or discrepancies in library processing may lead to a calculation that disagrees with the experimentally measuredbenchmark. This paper provides an overview of the processing and preparation of ENDF/B-VIII.0 incidentneutron data with NECP-Atlas and NJOY codes for implementation in the MCNP code. The resulting libraries are statistically inter-compared and tested by conducting benchmark calculations, as the mutualcomparison is a source of strong feedback for further improvements in processing procedures. Thedatabase of the benchmark experiments is based on a selection taken from the International Handbookof Evaluated Criticality Safety Benchmark Experiments (ICSBEP handbook) and those proposed by RussellD. Mosteller. In general, there is quite good agreement between the NECP-Atlas1.2 and NJOY21(1.0.0.json)results with no substantial differences, if the correct input parameters are used
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참고문헌 (2)
참고문헌 신청
Kabach Ouadie / 2017 / Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016 / Nuclear Engineering and Technology 49(8):1610~1616
A. C. Kahler / 2017 / Monte Carlo Eigenvalue Calculations with ENDF/B-VI.8, JEFF-3.0, and JENDL-3.3 Cross Sections for a Selection of International Criticality Safety Benchmark Evaluation Project Handbook Benchmarks / Nuclear Science and Engineering 145(2):213~224
A. C. Kahler / 2017 / Monte Carlo Eigenvalue Calculations with ENDF/B-VI.8, JEFF-3.0, and JENDL-3.3 Cross Sections for a Selection of International Criticality Safety Benchmark Evaluation Project Handbook Benchmarks / Nuclear Science and Engineering 145(2):213~224
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