A unified Monte Carlo approach to fast neutron cross section data evaluation.

Smith, D. ; Argonne National Laboratory. Nuclear Engineering Division.

Argonne National Laboratory

关键词: Probability;    Fast Neutrons;    Cross Sections;    72 Physics Of Elementary Particles And Fields;    Entropy;   

DOI  :  10.2172/937403
RP-ID  :  ANL/NDM-166
RP-ID  :  DE-AC02-06CH11357
RP-ID  :  937403

美国|其它

来源: UNT Digital Library

【 摘 要 】

A unified Monte Carlo (UMC) approach to fast neutron cross section data evaluation that incorporates both model-calculated and experimental information is described. The method is based on applications of Bayes Theorem and the Principle of Maximum Entropy as well as on fundamental definitions from probability theory. This report describes the formalism, discusses various practical considerations, and examines a few numerical examples in some detail.