Neutron Penalty and Advantage Analysis of Candidate Accident-Tolerant Cladding Materials in PWRs

Ni Dongyang; Li Mancang; Wu Wenbin; Sun Wei

doi:10.13832/j.jnpe.2015.S2.0014

Volume 36 Issue S2

Feb. 2025

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Ni Dongyang, Li Mancang, Wu Wenbin, Sun Wei. Neutron Penalty and Advantage Analysis of Candidate Accident-Tolerant Cladding Materials in PWRs[J]. Nuclear Power Engineering, 2015, 36(S2): 14-16. doi: 10.13832/j.jnpe.2015.S2.0014

Citation:

Ni Dongyang, Li Mancang, Wu Wenbin, Sun Wei. Neutron Penalty and Advantage Analysis of Candidate Accident-Tolerant Cladding Materials in PWRs[J]. Nuclear Power Engineering, 2015, 36(S2): 14-16. doi: 10.13832/j.jnpe.2015.S2.0014

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Neutron Penalty and Advantage Analysis of Candidate Accident-Tolerant Cladding Materials in PWRs

doi: 10.13832/j.jnpe.2015.S2.0014

Science and Technology on Reactor Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2015-09-11
Rev Recd Date: 2015-11-18

Available Online: 2025-02-15

Abstract

Abstract

This paper analyzes the neutron penalty and advantage of the candidate accident–tolerant cladding materials 304 SS, 310 SS, FeCrAl, APMT and SiC. The results show that the sequence from high to low is: SiC＞Zr＞FeCrAl＞APMT＞304SS＞310SS. After using a thinner cladding of 0.4 mm and keeping a constant outer diameter, Fe-based alloys require an increase of no more than 0.5%, for achieving the same fuel cycle length [about 60000 MW·d/t（U）] as the zircaloy’s, while Si C requires less enriched uranium about 0.12% by using a standard cladding thickness.
- Candidate accident-tolerant cladding materials,
- Neutron penalty and advantage,
- PWRs