| dc.description.abstract | Neutronic analysis on the Molten Salt Reactor
FUJI-12 using the fissile material 235U in LiFBeF2-UF4 has been carried out. The problem
faced in the use of thorium-based fuel is that the
amount of 233U is small and not available in nature.
233U was produced through the 232Th breeding
at a cost of $46 million/kg. That is a very high
price when compared to 235U enrichment, which is
only $100/kg. The MSR FUJI-12 used in this study
is a generation IV reactor with a mixture of liquid
salt fuel LiF-BeF2-ThF4-UF4 and thorium-based
fuel ( 232Th+233U). In this study, neutronic analysis was carried out by replacing thorium-based fuel
with uranium-based fuel ( 235U+238U). Neutronic
analysis was performed using the OpenMC 0.13.0
code, which is a Monte Carlo simulation-based
neutron analysis code. The nuclear data library
used for neutronic calculations is ENDF B-VII/1.
The fuel is used in a LiF-BeF2-UF4 molten salt mixture with three eutectic compositions: fuel 1, fuel 2,
and fuel 3. Each fuel composition is optimized by
enriching 235U in UF4 by 3 % to 8 %. The optimization results show the stability of the reactor criticality value, which is the main parameter so that
the reactor can operate for the specified time. The
optimization results show that fuel 1 cannot reach
its optimal state in each variation of 235U enrichment.
Fuel 2 and fuel 3 can reach optimal conditions at
a minimum enrichment of 8 % and 7 % 235U. The
results of the analysis of the distribution of the neutron flux in the reactor core show the distribution
of nuclear reactions that occur in the core. The distribution of flux values in fuel 1 shows that the fission chain reaction is not running perfectly. Fuel 2
and fuel 3 are more stable by maintaining maximum flux at the center of the reactor core | en_US |
