The nuclear performance of a fusion-fission hybrid reactor having a molten salt composed of Na-Th-F-Be as the blanket fertile material an operating with a catalyzed deuterium-deuterium (DD) plasma is compared to a similar system utilizing a Li-Th-F-Be salt and operating with a deuterium-tritium (DT) plasma. The production of fissile fuel via the **2**3**2Th-**2**3**3U fuel cycle was considered on the basis of its potential nonproliferation aspects. The calculations were performed using one-dimensional discrete-ordinates methods to compare neutron balances, fuel production rates, energy deposition rates, and the radiation damage in the reactor structure.
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Condensed Matter Physics