Numerical Analysis of UN Fuel Performance

Tu Teng; Li Wenjie; Li Wei; Gao Shixin; Chen Ping

doi:10.13832/j.jnpe.2017.06.0185

Volume 38 Issue 6

Feb. 2025

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Tu Teng, Li Wenjie, Li Wei, Gao Shixin, Chen Ping. Numerical Analysis of UN Fuel Performance[J]. Nuclear Power Engineering, 2017, 38(6): 185-188. doi: 10.13832/j.jnpe.2017.06.0185

Citation:

Tu Teng, Li Wenjie, Li Wei, Gao Shixin, Chen Ping. Numerical Analysis of UN Fuel Performance[J]. Nuclear Power Engineering, 2017, 38(6): 185-188. doi: 10.13832/j.jnpe.2017.06.0185

Tu Teng, Li Wenjie, Li Wei, Gao Shixin, Chen Ping. Numerical Analysis of UN Fuel Performance[J]. Nuclear Power Engineering, 2017, 38(6): 185-188. doi: 10.13832/j.jnpe.2017.06.0185

Citation:

Tu Teng, Li Wenjie, Li Wei, Gao Shixin, Chen Ping. Numerical Analysis of UN Fuel Performance[J]. Nuclear Power Engineering, 2017, 38(6): 185-188. doi: 10.13832/j.jnpe.2017.06.0185

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Numerical Analysis of UN Fuel Performance

doi: 10.13832/j.jnpe.2017.06.0185

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2017-03-07
Rev Recd Date: 2017-09-23

Available Online: 2025-02-09

Abstract

Abstract

Uranium nitride is an important candidate for Accident Tolerant Fuels（ATF） due to its high thermal conductivity and high heavy metal（HM） density. This paper introduced an enhancement of FUPAC by incorporating UN material property correlations and irradiation models. Some preliminary analyses of UN fuel performance at steady-states were also performed, and the results showed that UN fuel has good performance in aspects like fuel temperature, fission gas release, fuel rod pressure and cladding strain. Finally, future research and development works for UN fuel are discussed in this paper.
- UN fuel,
- ATF,
- Fuel performance analysis