Probability tables, pointwise and multigroup neutron cross sections in the Monte Carlo code TRIPOLI-3

摘要

The neutron cross section processing method is very important in the shielding and neutronic calculations. Parallel to the traditional multigroup and pointwise method, the probability table method has been developed for the unresolved resonance energy rate. Its advantage is to present properly the neutron cross section fluctuations within a given energy group, allowing a correct calculation of the self-shielding effect. In the other hand, it is easy to be used in the Monte Carlo calculations. In this paper, some examples are calculated by the Monte Carlo transport code TRIPOLI-3 using the multigroup, pointwise cross sections and the probability tables. It is proved that the probability table method is valid not only in the unresolved resonances range but also in the resolved resonance range. (authors) 10 figs., 7 tabs., 10 refs. (Atomindex citation 26:053532)