• NUCLEAR TECHNIQUES
  • Vol. 46, Issue 5, 050601 (2023)
Mengfei ZHOU, Guoming LIU*, and Xiaodong HUO
Author Affiliations
  • China Nuclear Power Engineering Co. Ltd., Beijing 100840, China
  • show less
    DOI: 10.11889/j.0253-3219.2023.hjs.46.050601 Cite this Article
    Mengfei ZHOU, Guoming LIU, Xiaodong HUO. Design and neutronics characteristics analysis of the fuel assembly in gas-cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(5): 050601 Copy Citation Text show less

    Abstract

    Background

    The gas-cooled fast reactor (GFR) has great advantages of finance and sustainability which combines the features of high temperature gas-cooled reactor and fast reactor. However, safety issue has become the main challenge in the development of GFR due to the high temperature and high neutron flux in the GFR core. Coated particle fuel (CPF) has been widely used in high temperature reactor (HTR) due to the excellent high temperature tolerance.

    Purpose

    In order to strengthen the safety property in GFR, this paper puts forward a block-type fuel assembly (FA) model based on CPF. Based on the FA model, neutronics analysis and thermal hydraulics validation is carried out to verify the rationality of the design.

    Methods

    Monte Carlo method is used in the calculation. Physical parameters including plutonium fraction in the U-Pu mixture fuel, diameter of fuel pins/coolant channels, the number of coolant channels, pitch-to-diameter ratio, thickness of cladding and thickness of assembly wrapper were selected and sensitivity analysis were conducted on the FA property to these parameters.

    Results

    Analysis results show that among the above six parameters, plutonium fraction and pitch-to-diameter ration have the most obvious effect on the neutronic property and the number of the coolant channels mainly influences the power distribution of the GFR FA. Finally, temperature distribution of the FA is calculated using single channel model under a low coolant fraction and requirements in terms of thermal-hydraulic property are put forward for the FA parameters.

    Conclusions

    The block-type FA model put forward in this paper meets the design requirements well. The research conclusion of this paper provides reference for the future study on GFR nuclear design.

    Mengfei ZHOU, Guoming LIU, Xiaodong HUO. Design and neutronics characteristics analysis of the fuel assembly in gas-cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(5): 050601
    Download Citation