Neutronic analysis of thorium nitride (Th-233U)N and thorium-plutonium nitride (Th-Pu-233U)N fuel for 200 MWth long-life pressurized water reactors has been done. PWR is the most dominantly used reactor in the world and one of three types of light water reactor. In this study, we compared the neutronic analysis of two fuel type i.e., thorium nitride (Th-233U)N and thorium-plutonium nitride (Th-Pu-233U)N. The neutronic calculation performed using the SRAC code system based on library SRACLIB-JENDL 4.0. The calculations performed in this study shows that thorium-plutonium nitride fuel has greater initial excess reactivity than thorium nitride fuel. Thorium nitride fuel can be operated for more than 20 years, while thorium-plutonium nitride fuel can be operated for 17 years. The utilization of heterogeneous core configuration at the PWR system makes energy distribution become relatively flattered compared to homogeneous fuel configuration.

Topics
Pressurized water reactors, Nitrides, Chemical elements, Libraries
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