Department of Nuclear EngineeringIn this paper, the verification and validation of ENDF/B-VIII.0 XS data uses STREAM code and MCS code. ENDF/B-VIII.0 XS data compare with ENDF/B-VII.1 XS data. In the case of a library of unique nuclear data for STREAM, the neutron transport analysis code, ENDF files for each nuclide were produced in Group-wise XS using NJOY code system, and in the second step, STREAM XS Library was produced using STREAM library production system, NTOS. Using this multi-group nuclear data production system, STREAM XS library was produced for all nuclides based on ENDF/B-VII.1 nuclear data library and ENDF/B-VIII.0 nuclear data library. To assess the accuracy of the library, STREAM code and MCS code were simultaneously compared for each ENDF version.
For the validation, each of benchmarks are used, NCA benchmark, VERA benchmark and ICSBEP benchmark. NCA benchmark analysis, which is the critical experiments performed at the Toshiba Nuclear Critical Assembly (NCA) critical facility. Each benchmark was compared in STREAM and MCS, and NCA benchmark analysis include tungsten gray rods demonstrates the accuracy of STREAM code???s pin power distribution. STREAM code nuclear source used the both of ENDF/B-VIII.0 and ENDF/B-VII.1, and their results compared with each of MCS code results.
When STREAM's results were compared for each version of ENDF, NCA benchmark found that the difference of the effective multiplication factor was within 100 pcm for the problem, confirming that ENDF/B-VIII.0 STREAM XS Library was properly produced. Also in case of VERA benchmark and ICSBEP benchmark, the difference of the effective multiplication factor was within 300 pcm for the problem with ENDF/B-VII.1 XS Library results and ENDF/B-VIII.0 XS Library results. The accuracy of STREAM results was verified by comparing them with the MCS results of the same problem for each result.ope
