Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Basic research on utilization of thorium-based nuclear fuel

Zhang, J.H.; Bao, B.R.; Xia, Y.X.; Wang, G.Q.; Zhu, J.B. (Academia Sinica, Shanghai, SH (China). Shanghai Inst. of Nuclear Research)

Abstract

The dependences of build-up of U-233, U-232, Pa-233 and fission products on integral neutron flux for ThO₂ samples irradiated in high flux ETR at constant neutron flux and steady spectrum have been investigated. From these experiments, we have accumulated experiences on further research for the behaviours of the irradiated ThO₂ under different irradiation conditions in reactor.

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key words: breeding ratio; experimental data; fast neutrons; neutron flux; protactinium 233; thermal neutrons; thorium oxides; uranium 232; uranium 233

Reference:: Proceedings of a technical committee meeting on utilization of thorium-based nuclear fuel: current status and perspectives held in Vienna, 2-4 December 1985; International Atomic Energy Agency, Vienna (Austria); IAEA-TECDOC--412, pp:67-72