Thorium, in this case, 232Th has a higher thermal neutron capture
cross-section than 238U, which means that more fertile isotopes can be
transmuted and could lead to higher fissile isotope 233U. In addition,
233U has a good performance in the thermal spectrum. Theoretically, a
nuclear reactor using thorium fuel can also last longer than one using
uranium fuel. The use of TRISO duplex fuel is predicted to produce better
neutronic behavior in a pebble bed reactor. This work aims to study the
kinetic parameters of a pebble bed reactor with TRISO duplex fuel. The
configuration of the TRISO duplex fuel pebble consists of an inner region
filled with UO2 TRISO particles and an outer region filled with
ThO2 TRISO particles surrounded by a graphite matrix of fuel pebble.
Three configurations with volume fraction of UO2-ThO2 were considered in
this study: 80-20 %, 75-25 %, and 70-30 %. The HTR-10 reactor was chosen
as a reactor model because its geometry and material
specifications are known. A series of calculations were conducted
using the Monte Carlo transport code MCNP6 and ENDF/B-VII.1 nuclear
data library. The calculation results were then analyzed to investigate the
effect of UO2 and ThO2 compositions in TRISO duplex fuel on the kinetic
parameters of the pebble bed reactor with various TRISO packing fractions of
1-50 %. It can be concluded that the utilization of TRISO duplex fuel in a
pebble bed reactor could significantly affect the core multiplication
factor and kinetic parameters caused by an increase in Th content. On the
other hand, the TRISO packing fraction is taking part in neutron moderation since a lower packing fraction means higher moderation for fueled
pebble.