Production of neutron cross section library based on JENDL-4.0 to continuous-energy Monte Carlo code MVP and its application to criticality analysis of benchmark problems in the ICSBEP handbook
Okumura, Keisuke ; Nagaya, Yasunobu
In May 2010, JENDL-4.0 was released from JAEA as the updated Japanese Nuclear Data Library. It was processed by the nuclear data processing system LICEM and an arbitrary-temperature neutron cross section library MVPlib_nJ40 was produced for the neutron and photon transport calculation code MVP based on the continuous-energy Monte Carlo method. The library contains cross sections for 406 nuclides on the free gas model, thermal scattering cross sections, and cross sections of pseudo fission products for burn-up calculations with MVP. Criticality benchmark calculation was carried out with MVP and the produced library for about 1,000 cases of critical experiments stored in the ICSBEP handbook, which covers a wide variety of fuel materials, fuel forms, and neutron spectra. We report all comparison results of effective neutron multiplication factors between calculations and experiments to give a validation data for the prediction accuracy of JENDL-4.0 for criticalities.