MCNP(trademark) ENDF/B-VI validation: Infinite media comparisons of ENDF/B-VI and ENDF/B-V

摘要

Infinite media calculations have been performed to validate the new MCNP ENDF/B-VI Library, ENDF60. All 124 nuclides have neutron flux and heating tallies compared against ENDF/B-V, as well as the MCNP Recommended Data Sets when these were not ENDF/B-V. For nuclides with photon production, photon flux and heating tallies have also been compared. All significant differences between the new ENDF60 results and those obtained with other data sets are discussed. This report provides a method for data comparison so that a better decision can be made as to the best data set to be used for a particular problem.