Nuclear Engineering and Technology

  • 제53권4호
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  • Pages.1236-1249
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  • 2021
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code

  • Chen, Ping (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, And Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University) ;
  • Qiu, Bowen (Science and Technology on Reactor System Design Technology Laboratory) ;
  • Li, Yuanming (Science and Technology on Reactor System Design Technology Laboratory) ;
  • Wu, Yingwei (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, And Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University) ;
  • Hui, Yongbo (Science and Technology on Reactor System Design Technology Laboratory) ;
  • Deng, Yangbin (Advanced Nuclear Energy Research Team, Department of Nuclear Science and Technology, Collage of Physics and Optoelectronic Engineering, Shenzhen University) ;
  • Zhang, Kun (Science and Technology on Reactor System Design Technology Laboratory)
  • 투고 : 2020.04.25
  • 심사 : 2020.09.20
  • 발행 : 2021.04.25
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초록

Although there are still controversial opinions and uncertainty on application of SiCf/SiC composite cladding as next-generation cladding material for its great oxidation resistance in high temperature steam environment and other outstanding advantages, it cannot deny that SiCf/SiC cladding is a potential accident tolerant fuel (ATF) cladding with high research priority and still in the engineering design stage for now. However, considering its disadvantages, such as low irradiated thermal conductivity, ductility that barely not exist, further evaluations of its in-pile behaviors are still necessary. Based on the self-developed code we recently updated, relevant thermohydraulic and mechanical models in FROBA-ATF were applied to simulate the cladding behaviors under normal and accident conditions in this paper. Even through steady-state performance analysis revealed that this kind of cladding material could greatly reduce the oxidation thickness, the thermal performance of UO2-SiC was poor due to its low inpile thermal conductivity and creep rate. Besides, the risk of failure exists when reactor power decreased. With geometry optimization and dopant addition in pellets, the steady-state performance of UO2-SiC was enhanced and the failure risk was reduced. The thermal and mechanical performance of the improved UO2-SiC was further evaluated under Loss of coolant accident (LOCA) and Reactivity Initiated Accident (RIA) conditions. Transient results showed that the optimized ATF had better thermal performance, lower cladding hoop stress, and could provide more coping time under accident conditions.

키워드

과제정보

This research was supported by the National Key Research and Development Program of China (No.2019YFB1901000) and also supported by China Natural Science Foundation under Grand No.U1867219.

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