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

【 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.