Minimum Required Burnup Analysis of Liquid-fueled Molten Chlorine Salt Fast Reactor

Peng Yu; Zhu Guifeng; Niu Miaomiao

doi:10.13832/j.jnpe.2022.05.0051

Volume 43 Issue 5

Oct. 2022

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Peng Yu, Zhu Guifeng, Niu Miaomiao. Minimum Required Burnup Analysis of Liquid-fueled Molten Chlorine Salt Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(5): 51-55. doi: 10.13832/j.jnpe.2022.05.0051

Citation:

Peng Yu, Zhu Guifeng, Niu Miaomiao. Minimum Required Burnup Analysis of Liquid-fueled Molten Chlorine Salt Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(5): 51-55. doi: 10.13832/j.jnpe.2022.05.0051

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Minimum Required Burnup Analysis of Liquid-fueled Molten Chlorine Salt Fast Reactor

doi: 10.13832/j.jnpe.2022.05.0051

1.
Nanjing Institute of Technology, Nanjing, 211167, China
2.
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China

Received Date: 2021-09-24
Rev Recd Date: 2022-04-08
Publish Date: 2022-10-12

Abstract

Abstract

In order to explore the average discharge burnup depth of liquid-fueled molten chlorine salt fast reactor operating in the breed-and-burn mode, based on the neutron balance analysis method, five common chlorine salts are selected, and the scheme of online removal of fission gas and insoluble fission products is proposed to maintain the breed-and-burn operation mode. The effects of heavy metal density of chloride salt and online treatment scheme on minimum required burnup and acceptable core neutron loss term for maintaining the breed-and-burn mode in the infinite cell model are mainly studied and analyzed. The analysis shows that the minimum required burnup of 68NaCl-32UCl₃ and 20UCl₃-80UCl₄ is 30.47% FIMA (FIMA refers to the ratio of the number of fissioned atoms to the total number of initially loaded metal atoms) and 10.28% FIMA respectively; After removing fission gas and insoluble fission products, the acceptable neutron loss term for 60NaCl-40UCl₃ is increased from 3.49% to 10.68%. The results show that the density of heavy metals in chloride salts has a significant impact on the minimum required burnup, and the removal of fission gases and insoluble fission products can greatly improve the neutron economy of the fuel salt system, and at the same time, improve the acceptable core neutron loss term for the breed-and-burn operation mode.
- Molten chlorine salt fast reactor,
- Neutron balance analysis method,
- Minimum required burnup,
- Breed-and-burn

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References(7)

References

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