A Physics Study of a 600-MW(thermal) Gas-Cooled Fast Reactor
Abstract
A neutronic feasibility study was performed for a 600-MW(thermal) gas-cooled fast reactor
fuel cycle through recycling simulations. Sensitivity calculations were also performed for various physics
design parameters such as the plutonium volume fraction of the fuel, fuel burnup, core material volume
fraction, and the power density. The results showed that the initial breeding gain of0.04755 is sufficient
to sustain the recycling of the actinides with a reasonable amount of natural uranium and plutonium feed
material. The comparative calculation on the core power density has shown that it is feasible to reduce
the amount of minor actinides and spent fuel in the high power density core (98.4 MW/m3) compared to the
reference core (58.2 MW/m3). It was also found that the fuel cycle cost is saved by 0.4 mills/kW{h for
the high power density core compared to the reference core.