Research on the Key Influencing Factors of the Driving Force of the Primary Loop System of the Natural Circulation Lead-based Fast Reactor

Zhai Pengdi; Zhu Enping; Zhao Pengcheng; Wang Tianshi; Yu Tao

doi:10.13832/j.jnpe.2022.03.0066

Volume 43 Issue 3

Jun. 2022

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Zhai Pengdi, Zhu Enping, Zhao Pengcheng, Wang Tianshi, Yu Tao. Research on the Key Influencing Factors of the Driving Force of the Primary Loop System of the Natural Circulation Lead-based Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(3): 66-73. doi: 10.13832/j.jnpe.2022.03.0066

Citation:

Zhai Pengdi, Zhu Enping, Zhao Pengcheng, Wang Tianshi, Yu Tao. Research on the Key Influencing Factors of the Driving Force of the Primary Loop System of the Natural Circulation Lead-based Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(3): 66-73. doi: 10.13832/j.jnpe.2022.03.0066

Citation:

Zhai Pengdi, Zhu Enping, Zhao Pengcheng, Wang Tianshi, Yu Tao. Research on the Key Influencing Factors of the Driving Force of the Primary Loop System of the Natural Circulation Lead-based Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(3): 66-73. doi: 10.13832/j.jnpe.2022.03.0066

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Research on the Key Influencing Factors of the Driving Force of the Primary Loop System of the Natural Circulation Lead-based Fast Reactor

doi: 10.13832/j.jnpe.2022.03.0066

Zhai Pengdi^{1, 2
,},
Zhu Enping^{1, 2},
Zhao Pengcheng^{1, 2, 3
,
,},
Wang Tianshi^{1, 2},
Yu Tao¹

1.
School of Nuclear Science and Technology, University of South China, Hengyang, Hunan, 421001, China
2.
Cooperative Innovation Center for Nuclear Fuel Cycle Technology and Equipment, University of South China, Hengyang, Hunan, 421001, China
3.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2021-04-21
Accepted Date: 2021-06-06
Rev Recd Date: 2021-06-06
Publish Date: 2022-06-07

Abstract

Abstract

In order to deeply study the key factors affecting the driving force of the primary loop system of the natural circulation lead-based fast reactor, taking the natural circulation lead-based fast reactor SNCLFR-10 as the research object, a steady-state operation model describing the natural circulation of the primary loop of the reactor was constructed; The effects of heat transfer in cold/hot pool, nonlinear temperature distribution of heat source and heat sink and heat dissipation of reactor pressure vessel wall on natural circulation capacity are quantitatively analyzed theoretically, and relevant numerical simulation verification is carried out. The results show that the numerical simulation results are in good agreement with the theoretical calculation values in this study; the coupling effect of the three natural circulation capacity influencing mechanisms will reduce the natural circulation capacity of the SNCLFR-10 system, resulting in the relationship between natural circulation flow and power no longer satisfying the 1/3 power obtained by theory.

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References(15)

References

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