Accident tolerant fuel (ATF) cladding is a new type of nuclear fuel cladding designed to improve the safety and performance of nuclear reactors. In this paper, the kinetics and degradation mechanisms during high-temperature oxidation in steam of the three most promising ATF cladding materials, i.e., chromium-coated zirconium alloys, FeCrAl alloys, and silicon carbide-based composites, are described. Each system has its own degradation mechanisms leading to different maximum survival temperatures. After providing general information and data to understand the oxidation and degradation processes, illustrative examples obtained at the Karlsruhe Institute of Technology are given for each type of cladding. The maximum temperatures at which the barrier effect of the cladding can be maintained for a reasonable period of time during nuclear accident scenarios are 1200–1300 °C for Cr-coated Zr alloys, 1400 °C for FeCrAl alloys, and 1700 °C for SiC-based composite claddings.

事故容错燃料（ATF）包壳是一种新型核燃料包壳，旨在提高核反应堆的安全性和性能。本文描述了三种最有前途的 ATF 熔覆材料（即铬涂层锆合金、FeCrAl 合金和碳化硅基复合材料）在蒸汽中高温氧化的动力学和降解机制。每个系统都有自己的退化机制，导致不同的最大生存温度。在提供了了解氧化和降解过程的一般信息和数据后，针对每种类型的包层给出了在卡尔斯鲁厄理工学院获得的说明性示例。在核事故场景中，包壳的阻挡效应可以在合理时间内维持的最高温度为：Cr涂层Zr合金为1200-1300℃，FeCrAl合金为1400℃，SiC为1700℃。基复合材料包层。