Study for ²²⁸Th reduction in thermal reactor with Th-U fuel cycls

Study for 228 Th reduction in thermal reactor with Th-U fuel cycls 1 first-author China Institute of Atomic Energy, Beijing 102413 China Institute of Atomic Energy, Beijing 102413 By using computer code WIMS/CENDL, the effects of some parameters, core configuration such as fuel element structure, neutron flux and burn-up, are discussed in this paper. It is shown that high neutron flux, small fuel rod diameter, large volume ratio of coolant to fuel, seed-blank heterogeneous core arrangement and 231 Pa chemical separation are necessary for reducing 228 Th production in reactor. 228 Th Th-U fuel cycle Thermal reactor References PENG Shilu . Present status and prospects of nuclear power development in China . Proceedings of the sixth pacific basin nuclear conference , Beijing, China . Sep, 1987 Present status and prospects of nuclear power development in China Status and prospects of thermal breeders and their effect on fuel utilization , IAEA , Vienna , 1979 Status and prospects of thermal breeders and their effect on fuel utilization Status report on actinide and fission product transmutation studies, IAEA-TECDOC-984 , June, 1997 Status report on actinide and fission product transmutation studies, IAEA-TECDOC-984 Halsall M J , A Summary of WIMSD4 input options, AEEW-M1327 , 1980 A Summary of WIMSD4 input options, AEEW-M1327 This work is Supported by National Natural Science Foundation in China 1998-09-03 1999-02-01 2021-02-05 1999 Nuclear Science and Techniques 1 10