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RE-EVALUATION OF THE NEUTRONICS EXPERIMENTS FOR THE ITER SHIELDING BLANKET USING ENDF/B-VII, JEFF-3.1, AND JENDL-3.3

Title
RE-EVALUATION OF THE NEUTRONICS EXPERIMENTS FOR THE ITER SHIELDING BLANKET USING ENDF/B-VII, JEFF-3.1, AND JENDL-3.3
Author
김종경
Issue Date
2011-07
Publisher
AMER NUCLEAR SOC, 555 N KENSINGTON AVE, LA GRANGE PK, IL 60526 USA
Citation
FUSION SCIENCE AND TECHNOLOGY,Vol.60 No.1T//SUP [2011],80-83
Abstract
MCNP calculations for a benchmark representative of the fusion blanket neutronics shielding in SINBAD (Shielding Integral Benchmark Archive Database) were performed by using the four nuclear data libraries, ENDF/B-VII, JEFF-3.1, JENDL-3.3, and FENDL-2.1. Neutron and gamma flux spectra were calculated at two positions in a mock-up of the ITER inboard shield system. The results were compared with each other and also compared with measured data from the neutronics experiments for the ITER shielding blanket. For neutron spectra calculations, it is noted that the MCNPX calculations using all libraries agree well with experiments at positions A and B. For gamma spectra calculations, an overall good agreement can be stated and the tendency of a slight underestimation with penetration depth is observed
URI
http://www.tandfonline.com/doi/abs/10.13182/FST11-A12409http://hdl.handle.net/20.500.11754/35952
ISSN
1536-1055; 1943-7641
DOI
10.13182/FST11-A12409
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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