Progess in MCORGS Code and Blanket Conceptual Research on Fusion Fission Hybrid Reactor for Energy

Fusion fission hybrid reactor for energy (FFHR E) is fueled by natural uranium and cooled by light water. A three dimensional code MCORGS, which is coupled by MCNP and ORIGENS, has been adopted in neutronics analysis of the three dimensional blanket model for FFHR-E. An simplified pyro-reprocessing scheme was suggested. It is expected that the spent fuel can be heated up to 2 100 K by its decay heat, then the fission product elements whose boiling points below this temperature will be evaporated. The displacement per atom (dpa) of the blanket materials was evaluated. A reload period around ten years is suggested, and the spent fuel can be reused multiple times after reprocessing. The average tritium breeding ratio (TBR) is about 1.15 and the blanket energy multiplication is about 12 in the first fuel reload cycle. While in the 2nd to 9th fuel reload cycles, the average TBR and M are 1.35 and 18 respectively. Computational fluid dynamics code was used in CAD modeling, meshing, and steady state heat transfer analysis. The maximal temperatures in different zones are all lower than their allowable values and have reasonable margins.