Analysis of different nuclear data libraries on the Fluoride-salt-cooled high-temperature reactor

This work presents a comparison of Fluoride-salt-cool High-temperature Reactor (FHR) system calculations using the ENDF/B-VII.1, JEFF-3.2, JEFF-3.3 and ENDF/B-VIII.0 nuclear data libraries. Analysis of a simplified model of the Shanghai Institute of Applied Physics TMSR-SF1 reactor using both Serpent and MCNP was performed. Unit cell and full core models based on a specification developed at the University of California, Berkeley were used in this work. The use of the newer cross section libraries produced an increase of thermal fission of 235U by 0.5-1%. The reactivity of the system in a fresh configuration was increased by 270-600 pcm, thermal flux was reduced by ∼1% and the effect on reactivity of the system as a function of 7Li purity of salt coolant was also reduced by ∼2%. Neutron leakage, reaction rates, neutron flux spectra, thermal flux distributions and the effect of spatially homogenising regions of the system were also calculated and analysed.