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Benchmark of neutron transport simulation capability of super Monte Carlo calculation program SuperMC2.0

  • Guang Yao Sun
  • , Jing Song
  • , Hua Qing Zheng
  • , Zhen Ping Chen
  • , Li Juan Hao
  • , Peng Cheng Long
  • , Li Qin Hu
  • , Yi Can Wu
  • University of Science and Technology of China
  • Chinese Academy of Sciences

Research output: Contribution to journal › Article › peer-review

21 Scopus citations

Abstract

Super Monte Carlo calculation program for nuclear and radiation process (SuperMC2.0) developed by FDS team is a radiation transport code based on Monte Carlo method. A series of testing samples, such as critical safety, neutron integral leakage benchmarks and IAEA-ADS, were used to verify the neutron transport simulation of SuperMC2.0. The results of SuperMC2.0 are in accordance with the results of MCNP and experiments. The correctness of neutron transport in SuperMC2.0 is preliminarily verified.

Original languageEnglish
Pages (from-to)520-525
Number of pages6
JournalYuanzineng Kexue Jishu/Atomic Energy Science and Technology
Volume47
Issue numberSUPPL.
DOIs
StatePublished - 2013

Keywords

  • Benchmark
  • Monte Carlo
  • Neutron transport

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