Neutronics Calculation of Fusion-Fission Hybrid Breeding Thorium Fuel Assembly

MA Xubo; CHEN Yixue; QUAN Guoping; WANG Yue; HAN Jingru; LU Daogang

Mar. 2025

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MA Xubo, CHEN Yixue, QUAN Guoping, WANG Yue, HAN Jingru, LU Daogang. Neutronics Calculation of Fusion-Fission Hybrid Breeding Thorium Fuel Assembly[J]. Nuclear Power Engineering, 2012, 33(1): 129-133.

Citation:

MA Xubo, CHEN Yixue, QUAN Guoping, WANG Yue, HAN Jingru, LU Daogang. Neutronics Calculation of Fusion-Fission Hybrid Breeding Thorium Fuel Assembly[J]. Nuclear Power Engineering, 2012, 33(1): 129-133.

Citation:

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Neutronics Calculation of Fusion-Fission Hybrid Breeding Thorium Fuel Assembly

School of Nuclear Science and Technology, North China Electric Power University, Beijing 102206, China

Received Date: 2010-10-11
Rev Recd Date: 2011-04-14

Available Online: 2025-03-08

Abstract

Abstract

A preliminary comparative study of the physical properties among 17×17 fuel assembly in PWRs for prototype between uranium assembly and hybrid breeding thorium-based assembly has been investigated respectively using the DRAGON software.The parameters such as fuel temperature coefficient,moderator temperature coefficient and that variation as a function of operation period have been investigated.Results show that the neutron properties of uranium-based assembly and hybrid breeding thorium-based assembly are similitude,but MA mass of hybrid breeding thorium-based assembly is evidently less than those of the uranium assembly.
- Fusion-fission hybrid breeding thorium fuel,
- Neutronics,
- Temperature coefficient