Integral Data Benchmark of HENDL2.0/MG Compared with Neutronics Shielding Experiments

【摘要】 <正> HENDL2.0, the latest version of the hybrid evaluated nuclear data library, wasdeveloped based upon some evaluated data from FENDL2.1 and ENDF/B-Ⅶ. To qualify andvalidate the working library, an integral test for the neutron production data of HENDL2.0 wasperformed with a series of existing spherical shell benchmark experiments (such as V, Be, Fe, Pb,Cr, Mn, Cu, A1, Si, Co, Zr, Nb, Mo, W and Ti). These experiments were simulated numericallyusing HENDL2.0/MG and a home-developed code VisualBUS. Calculations were conducted withboth FENDL2.1/MG and FENDL2.1/MC, which are based on a continuous-energy Monte CarloCode MCNP/4C. By comparison and analysis of the neutron leakage spectra and the integral test,benchmark results of neutron production data are presented in this paper.更多还原

【Abstract】 HENDL2.0, the latest version of the hybrid evaluated nuclear data library, was developed based upon some evaluated data from FENDL2.1 and ENDF/B-Ⅶ. To qualify and validate the working library, an integral test for the neutron production data of HENDL2.0 was performed with a series of existing spherical shell benchmark experiments (such as V, Be, Fe, Pb, Cr, Mn, Cu, A1, Si, Co, Zr, Nb, Mo, W and Ti). These experiments were simulated numerically using HENDL2.0/MG and a home-developed code VisualBUS. Calculations were conducted with both FENDL2.1/MG and FENDL2.1/MC, which are based on a continuous-energy Monte Carlo Code MCNP/4C. By comparison and analysis of the neutron leakage spectra and the integral test, benchmark results of neutron production data are presented in this paper.更多还原