抄録
The concept of multi-generation reprocessing in spent fuel for ceramic fast reactor is proposed in this paper. This reprocessing can deal with the spent fuel effectively with the simple and economic high-temperature dry (HT-dry) reprocessing without fine separation. After removing partial fission products from spent fuel by the HT-dry reprocessing, the new fuel can be used as the initial fuel for the next generation for the ceramic reactors, in which the fuel can be burned for decades. Based on the ceramic coolant fast reactor, this paper studies the neutron physics performance for multi-generation removing fission products. The parameters of the study includes Keff, beam density, nuclide mass. The results show the greater the removal amount, the higher the peak of the Keff, and the longer the duration of the continuous combustion. This preliminarily can prove the feasibility of the concept of this fuel cycle and meet the need of the nuclear energy strategy.
