Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2018, Vol. 29 ›› Issue (1): 16 doi: 10.1007/s41365-017-0351-3

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles    

Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core

Kang-Li Shi, Shu-Zhou Li, Xi-Lin Zhang, Peng-Cheng Zhao, Hong-Li Chen   

  1. School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China
  • Contact: Kang-Li Shi E-mail:shikl@mail.ustc.edu.cn
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Kang-Li Shi, Shu-Zhou Li, Xi-Lin Zhang, Peng-Cheng Zhao, Hong-Li Chen. Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core.Nuclear Science and Techniques, 2018, 29(1): 16     doi: 10.1007/s41365-017-0351-3

Abstract:

In this paper, we perform an unprotected partial flow blockage analysis of the hottest fuel assembly in the core of the SNCLFR-100 reactor, a 100 MWth modular natural circulation lead-cooled fast reactor, developed by University of Science and Technology of China. The flow blockage shall cause a degradation of the heat transfer between the fuel assembly and the coolant potentially, which can eventually result in the clad fusion. An analysis of core blockage accidents in a single assembly is of great significance for LFR. Such scenarios are investigated by using the best estimation code RELAP5. Reactivity feedback and axial power profile are considered. The cross-sectional fraction of blockage, axial position of blockage, and blockage-developing time are discussed. The cladding material failure shall be the biggest challenge and shall be a considerable threat for integrity of the fuel assembly if the cross-sectional fraction of blockage is over 94%. The blockage-developing time only affects the accident progress. The consequence will be more serious if the axial position of a sudden blockage is closer to the core outlet. The method of analysis procedure can also be applied to analyze similar transient behaviors of other fuel-type reactors.

Key words: Transient analysis, Flow blockage, LFR, Natural circulation, RELAP5 code