Neutronics benchmarking study of breeding shield for the fusion experimental reactor (FER)

Neutron flux distribution and tritium breeding ratio (TBR) were calculated with the one-dimensional discrete ordinates code using the various cross section libraries and with the continuous energy Monte Carlo code. Two types of the geometrical representation were considered; one is the homogeneous mixture of structural material, aqueous lithium salt coolant and, if any, neutron multiplier; the other is the alternating layers of the structure and the coolant. Results were compared in terms of neutron flux attenuation, integrated TBR, and energy profile and spatial distribution of tritium production rate. SN/MC ratios of TBRs for the homogeneous model are smaller than unity by a few percents and several percents for the configurations with and without multiplier, respectively. For the heterogeneous model without multiplier, the total TBRs agree within several percents and are larger than those of the homogeneous model by 20-40%. While, total neutron fluxes are underestimated with SN calculatuins by 30-40% compared to the MC results for both the homogeous and heterogeneous models. (author). 14 refs.; 5 figs.; 5 tabs