THERMAL-hYDRAULIC AND NEUTRONIC SIMULATIONAND ANALYSIS OF BLANKETS OF FUSION ORFUSION-FISSION HYBRID REACTORS
XIAO BINGJIA QIU LIJIAN WU YICAN(Institute of Plasma Physics, Academia Sinica)
BITH code was developed for the blanket thermal-hydraulic and neutronic analysis of fusionor fusion-fission hybrid reactor, with BISON 1.5 neutronic code selected as reference code in neutronic transport. By modifying BISON 1.5 to consider the resonance shielding effect and substituting BISON1.5 data library and improving the fuel burning calculation method, BITH code can beused in the neutronic analysis of HLW transmutation and radiation damage etc. THPBHR code developed by the author was chosen as reference code in BITH thermal- hydraulic calculation . The systematical analysis of a reference blanket was also given.
【CateGory Index】： TL46