The calculation of neutron flux using Monte Carlo method

Abstract

Abstract. In this study, a hybrid reactor system was designed by using 99-95% Li 20 Sn 80 + 1-5% RG-Pu, 99-95% Li 20 Sn 80 + 1-5% RG-PuF 4 , and 99-95% Li 20 Sn 80 + 1-5% RG-PuO 2 fluids, ENDF/B-VII.0 evaluated nuclear data library and 9Cr2WVTa structural material. The fluids were used in the liquid first wall, liquid second wall (blanket) and shield zones of a fusion-fission hybrid reactor system. The neutron flux was calculated according to the mixture components, radial, energy spectrum in the designed hybrid reactor system for the selected fluids, library and structural material. Three-dimensional nucleonic calculations were performed using the most recent version MCNPX-2.7.0 the Monte Carlo code.

Calculation of Fissile Fuel Production in Some Minor Actinides Based on Thorium

“…Fusion neutrons collide with the liquid wall. Thus, with the hybrid reactor, both energy, fuel and short-lived wastes are generated (Şahin, 2007;Nygren et al, 2004;Hill et al, 2009;Günay, 2013;Günay, 2014c;Günay and Bardakçı, 2017).…”