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The Testing and Application of Continuous-Energy Neutron Cross Section Library HENDL-ADS/MC

[+] Author Affiliations
Chong Chen

University of Science and Technology of China, Hefei, Anhui, ChinaChinese Academy of Sciences, Hefei, Anhui, China

Jun Zou, Dezheng Xu, Qin Zeng, Minghuang Wang

Chinese Academy of Sciences, Hefei, Anhui, China

Paper No. ICONE21-16514, pp. V002T05A057; 7 pages
  • 2013 21st International Conference on Nuclear Engineering
  • Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors
  • Chengdu, China, July 29–August 2, 2013
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5579-9
  • Copyright © 2013 by ASME


A point-wise cross-section data library HENDL-ADS/MC (Hybrid Evaluated Nuclear Data Library) has been produced by FDS team to do the nuclear analysis for the ADS system. The HENDL-ADS/MC library contained 408 nuclide cross-section files including actinides, fission products and structural materials for neutron energy up to 150 MeV. The nuclear library also contained several sub-libraries with different temperatures. A series of neutron integral experiments and critical safety benchmarks have been performed to test the availability and reliability of the HENDL-ADS/MC data library. To validate and qualify the reliability of the high neutron energy cross section for HENDL-ADS/MC library further, a series of high neutron shielding experiments have been performed using MCNP. The testing results indicated the accuracy and reliability of HENDL-ADS/MC library.

Copyright © 2013 by ASME
Topics: Neutrons , Testing



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