Advanced Monte Carlo procedure for the IFMIF d-Li neutron source term based on evaluated cross section data

Abstract A newly developed computational procedure is presented for the generation of d-Li source neutrons in Monte Carlo transport calculations based on the use of evaluated double-differential d + 6,7 Li cross section data. A new code McDeLicious was developed as an extension to MCNP4C to enable neutronics design calculations for the d-Li based IFMIF neutron source making use of the evaluated deuteron data files. The McDeLicious code was checked against available experimental data and calculation results of McDeLi and MCNPX, both of which use built-in analytical models for the Li(d, xn) reaction. It is shown that McDeLicious along with newly evaluated d + 6,7 Li data is superior in predicting the characteristics of the d-Li neutron source. As this approach makes use of tabulated Li(d, xn) cross sections, the accuracy of the IFMIF d-Li neutron source term can be steadily improved with more advanced and validated data.