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CHEN Chao-bin, CHEN Yi-xue, HU Ze-hua, WU Jun, ZHANG Be-ai. Verification and Validation of ACEFormat Library Created From ENDF/BⅦ.0[J]. Atomic Energy Science and Technology, 2009, 43(9): 1-843. DOI: 10.7538/yzk.2009.43.09.0834
Citation: CHEN Chao-bin, CHEN Yi-xue, HU Ze-hua, WU Jun, ZHANG Be-ai. Verification and Validation of ACEFormat Library Created From ENDF/BⅦ.0[J]. Atomic Energy Science and Technology, 2009, 43(9): 1-843. DOI: 10.7538/yzk.2009.43.09.0834
shu

Verification and Validation of ACEFormat Library Created From ENDF/BⅦ.0

  • 1.

    Institute of Applied Physics and Calculational Mathematics, Beijing 100088, China

  • 2.

    Nuclear Science & Engineering School, North China Electric Power University, Beijing 102206, China

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  • Received Date: December 31, 1899
  • Revised Date: December 31, 1899
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    • Abstract
  • ENDF/BⅦ.0, released by the USA Cross Section Evaluation Working Group (CSEWG) in December 2006, was developed in five years since the previous release of ENDF/BⅥ.8 and was demonstrated to contain much better physical representations of the data and to perform much better than previus ENDF evaluations over a broad range of applications. We generated ACEformat pointwise cross section library from the ENDF/BⅦ.0 neutron reaction sublibrary with the processing code NJOY. The paper provides an overview of ENDF/BⅦ.0, a summary of the ACEformat files producing process and a detail description of the validation of the ACEformat library. The conclusion is that the ACEformat library produced is correct.
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    • References (5)
  • [1]
    1] THOMAS E B, JOHN T G, AVNEET S, et al. MCNP—A general MonteCarlo Nparticle transport code: Version 5, Volume Ⅱ，LACP030245[R]. New Mexico: Los Alamos National Laboratory, 2003.
    [2]
    MACFARLANE R E, MUIR D W. The NJOY nuclear data processing system: Version 91, LA12740M[R]. New Mexico: Los Alamos National Laboratory, 1994.
    [3]
    CHADWICK M B, OBLOINSKY P, HERMAN M, et al. ENDF/BⅦ.0: Next generation evaluated nuclear data library for nuclear science and technology[J]. Nuclear Data Sheets, 2006, 107: 2 9313 060.
    [4]
    THOMAS E B, JOHN T G, AVNEET S, et al. MCNP—A general MonteCarlo Nparticle transport code: Version 5, Volume Ⅲ，LACP030284[R]. New Mexico: Los Alamos National Laboratory, 2003.
    [5]
    BLAIR J B, MICHAEl A T, YOLANDA R, et al. International handbook of evaluated criticality safety benchmark experiments, NEA/NSC/DOC(95)03[R]. North Fremont: Nuclear Energy Agency, 2006.
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