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 ›› 2020, Vol. 31 ›› Issue (3): 32 doi: 10.1007/s41365-020-0741-9

• Invited Review Article • Previous Articles    

Recent studies on potential accident-tolerant fuel-cladding systems in light-water reactors

Sheng-Li Chen1,2 • Xiu-Jie He1 • Cen-Xi Yuan1   

  1. 1 Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, China
    2 Université Grenoble Alpes, I-MEP2, 38402 Saint Martin d’Hères, France
  • Received:2019-12-14 Revised:2020-01-22 Accepted:2020-01-22
  • Contact: Xiu-Jie He, Cen-Xi Yuan E-mail: hexiujie@mail.sysu.edu.cn (X. He), yuancx@mail.sysu.edu.cn (C. Yuan)
  • Supported by:
    This work was supported by the National Key Research and Development Program of China ( No. 2018YFB1900405), the National Natural Science Foundation of China (No. 11775316), the Tip-top Scientific and Technical Innovative Youth Talents of Guangdong Special Support Program ( No. 2016TQ03N575), the Fundamental Research Funds for the Central Universities (No. 19lgpy299), the Science and Technology Planning Project of Guangdong Province, China (No. 2019A050510022), and the Nuclear Power Institute of China (No. HT-ATF-14-2018001).
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Sheng-Li Chen, Xiu-Jie He, Cen-Xi Yuan. Recent studies on potential accident-tolerant fuel-cladding systems in light-water reactors.Nuclear Science and Techniques, 2020, 31(3): 32     doi: 10.1007/s41365-020-0741-9
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Abstract: Accident-tolerant fuel (ATF) has attracted considerable research attention since the 2011 Fukushima nuclear disaster. To improve the accident tolerance of the fuel-cladding systems in the current light-water reactors (LWRs), it is proposed to develop and deploy (1) an enhanced Zr-based alloy or coated zircaloy for the fuel cladding, (2) alternative cladding materials with better accident tolerance, and (3) alternative fuels with enhanced accident tolerance and/or a higher U density. This review presents the features of the current UO2-zircaloy system. Different techniques and characters to develop coating materials and enhanced Zr-based alloys are summarized. The features of several selected alternative fuels and cladding materials are reviewed and discussed. The neutronic evaluations of alternative fuel-cladding systems are analyzed. It is expected that one or more types of accident-tolerant fuel-cladding systems discussed in the present review will be implemented in commercial reactors.

Key words: Accident-tolerant fuel, Accident-tolerant 28 cladding, Light-water reactor, Neutronic evaluation