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

作　　者：Sheng-Li Chen Xiu-Jie He Cen-Xi Yuan 

机构地区：[1]Sino-French Institute of Nuclear Engineering and Technology,Sun Yat-sen University,Zhuhai 519082,China [2]Universite Grenoble Alpes,I-MEP2,38402 Saint Martin d’Heres,France

出　　处：《Nuclear Science and Techniques》2020年第3期94-123,共30页核技术（英文）

基　　金：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);the Nuclear Power Institute of China(No.HT-ATF-14-2018001)

摘　　要：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,it is proposed to develop and deploy(1)an enhanced Zrbased 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 ATF-cladding systems discussed in the present review will be implemented in commercial reactors.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, it is proposed to develop and deploy(1) an enhanced Zrbased 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 UO——2–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 ATF-cladding systems discussed in the present review will be implemented in commercial reactors.

关 键 词：Accident-tolerant fuel Accident-tolerant cladding Light-water reactor Neutronic evaluation 

分 类 号：TL421[核科学技术—核技术及应用]