Preliminary Study on Conceptual Design of Lead-based Fully Ceramic Microencapsulated Dispersion Fuel Core

Lou Lei; Wang Lianjie; Peng Xingjie; Zhao Chen; Zhang Bin; Zhou Bingyan; Zhou Nan; Hu Yuying; Wang Xingbo; Zhao Zifan

doi:10.13832/j.jnpe.2022.S2.0100

Volume 43 Issue S2

Dec. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(S2): 100-103

Lou Lei, Wang Lianjie, Peng Xingjie, Zhao Chen, Zhang Bin, Zhou Bingyan, Zhou Nan, Hu Yuying, Wang Xingbo, Zhao Zifan. Preliminary Study on Conceptual Design of Lead-based Fully Ceramic Microencapsulated Dispersion Fuel Core[J]. Nuclear Power Engineering, 2022, 43(S2): 100-103. doi: 10.13832/j.jnpe.2022.S2.0100

Citation:

Lou Lei, Wang Lianjie, Peng Xingjie, Zhao Chen, Zhang Bin, Zhou Bingyan, Zhou Nan, Hu Yuying, Wang Xingbo, Zhao Zifan. Preliminary Study on Conceptual Design of Lead-based Fully Ceramic Microencapsulated Dispersion Fuel Core[J]. Nuclear Power Engineering, 2022, 43(S2): 100-103. doi: 10.13832/j.jnpe.2022.S2.0100

Citation:

Lou Lei, Wang Lianjie, Peng Xingjie, Zhao Chen, Zhang Bin, Zhou Bingyan, Zhou Nan, Hu Yuying, Wang Xingbo, Zhao Zifan. Preliminary Study on Conceptual Design of Lead-based Fully Ceramic Microencapsulated Dispersion Fuel Core[J]. Nuclear Power Engineering, 2022, 43(S2): 100-103. doi: 10.13832/j.jnpe.2022.S2.0100

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Preliminary Study on Conceptual Design of Lead-based Fully Ceramic Microencapsulated Dispersion Fuel Core

doi: 10.13832/j.jnpe.2022.S2.0100

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

Received Date: 2022-07-20
Rev Recd Date: 2022-08-30
Publish Date: 2022-12-31

Abstract

Abstract

In order to make full use of the accident resistance characteristics of fully ceramic microencapsulated (FCM) dispersion fuel and further improve the safety of lead-based reactor, FCM fuel is applied to lead-based coolant reactor, and the preliminary conceptual design of lead-based FCM core is presented, and the fuel loading, fuel utilization, energy spectrum and reactivity of the FCM core are compared with the traditional lead-based UO₂ fuel core. The comparison results show that FCM has a little moderating effect on core energy spectrum, and high enrichment UO₂ fuel core is needed to ensure that the core ²³⁵U loading meets the energy output requirements. The ²³⁵U loading of the core using FCM is lower than that of UO₂ core, and the fuel utilization rate is further improved. Finally, the power flattening optimization of lead-based FCM core layout is carried out, and the core power is flattened by radial FCM phase volume partition. The calculation results show that the core power peak factor (F_Q) is reduced from 2.43 to 1.93, and the core nuclear enthalpy rise factor (F_DH) is reduced from 1.79 to 1.33.
- Lead-based reactor,
- Fully ceramic microencapsulated (FCM) fuel,
- Primary conceptual design,
- Power flattening,
- Phase volume partition

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References(8)

References

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