科技报告详细信息
ENDF/B Thermal Data Testing
McCrosson, F.J.
Savannah River Site (S.C.)
关键词: Data Analysis;    Uranium;    Testing;    Nuclear Data Collections;    Cross Sections;   
DOI  :  10.2172/787923
RP-ID  :  DP-MS-75-14
RP-ID  :  AT(07-2)-1
RP-ID  :  787923
美国|英语
来源: UNT Digital Library
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【 摘 要 】

The thermal data testing group is concerned with establishing the merit of ENDF/B cross sections for the analysis of thermal systems. The integral experiments used in the testing are designed to analyze each of the phenomena identified in the familiar four-factor formula. For brevity, only the testing of the cross sections in uranium systems is described in this report.

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