The Neutron Spectrum from a Fission Source in Graphite
作者:
ProfioA. E.,
AntúnezH M.,
HuffmanD. L,
期刊:
Nuclear Science and Engineering
(Taylor Available online 1969)
卷期:
Volume 35,
issue 1
页码: 91-103
ISSN:0029-5639
年代: 1969
DOI:10.13182/NSE69-A21117
出版商: Taylor&Francis
数据来源: Taylor
摘要:
AbstractTime-of-flight measurements of the neutron angular flux spectrum in graphite have been made to provide a standard of comparison for neutron penetration calculations. The spectrum from 0.002 eV to 15 MeV was measured with an accuracy of±13 to 32% and a resolution of±2 to 10%, at angles from 0 to 60°and penetrations to 66 cm. Comparisons with Monte Carlo and discrete ordinates calculations using ENDF/B cross sections indicate fairly good agreement except in resonances and near zero degrees for discrete ordinates. Scalar fluxes have also been calculated with the moments method.
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