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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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