Design and producing of fine-group cross section library HENDL3.0/FG for subcritical system

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22105912

Zou, J.; Zeng, Q.; Xu, D.; Hu, L.; Long, P. ^[1]

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1. Inst. of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China)

To improve the accuracy of the neutron analyses for subcritical system with thermal fission blanket, a coupled neutron and photon (315 n + 42{gamma}) fine-group cross section library HENDL3.0/FG based on ENDF/B-VII, JEFF3.1 and JENDL3.3 was produced by FDS team. In order to test the availability and reliability of the HENDL3.0/FG data library, shielding and critical safety benchmarks were performed with VisualBUS code. The testing results indicated that the discrepancy between calculation and experimental values of nuclear parameters fell in a reasonable range. It showed that the nuclear data library had accuracy and availability. (authors)

• Research Organization: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
• OSTI ID: 22105912
• Resource Relation: Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 27 refs.
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
ACCURACY
BENCHMARKS
DESIGN
NEUTRONS
NUCLEAR DATA COLLECTIONS
PHOTONS
SELF-SHIELDING
SHIELDING
TESTING
THERMAL FISSION