The FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently developed in Japan. This paper reports on the progress of the development of accident tolerant FeCrAl-ODS fuel claddings for boiling water reactors (BWRs) in Japan.

Both experimental and analytical studies were conducted to evaluate the influence of implementation of the FeCrAl-ODS fuel cladding to the current BWRs.

In the experimental study, key material properties of FeCrAl-ODS fuel cladding have been obtained and accumulated using bar, sheet and tube-shaped materials to support the evaluations in the analytical study. In the evaluation at normal operating conditions, strength and ductility, corrosion property, tritium permeability, wear property, resistance to iodine stress corrosion cracking (SCC) and weldability were examined. A preliminary assessment of compatibility of the FeCrAl-ODS fuel cladding with the current recycling system in Japan was also conducted. In the evaluation of the design basis accident and the beyond design basis accident, strength, steam oxidation property, resistance to water quenching during a loss-of-coolant accident (LOCA) and the LOCA burst property were examined.

In order to evaluate the influence of implementation of the FeCrAl-ODS cladding to the current BWRs, the core characteristics and the fuel behavior were evaluated in the analysis study at the normal operating condition. The analysis for the 9 × 9-type and the 10 × 10-type fuel assemblies and the reactor type of the Advanced BWR (ABWR) revealed a good applicability of FeCrAl-ODS fuel cladding.

Finally, the challenges and perspectives found in the program are highlighted to enhance international collaborations to promote the development of the FeCrAl-ODS fuel cladding.

FeCrAl 氧化物弥散强化 (ODS) 合金是用于轻水反应堆 (LWR) 的容灾燃料 (ATF) 包壳的一种很有前途的候选合金，最近在日本得到了开发。本文报告了日本沸水反应堆 (BWR) 事故容错 FeCrAl-ODS 燃料包壳的开发进展。

进行了实验和分析研究以评估实施 FeCrAl-ODS 燃料包壳对当前 BWR 的影响。

在实验研究中，使用棒状、片状和管状材料获得并积累了 FeCrAl-ODS 燃料包壳的关键材料特性，以支持分析研究中的评估。在正常操作条件下的评估中，检查了强度和延展性、腐蚀性能、氚渗透性、耐磨性、抗碘应力腐蚀开裂 (SCC) 性和可焊性。还对 FeCrAl-ODS 燃料包壳与日本当前回收系统的兼容性进行了初步评估。在设计基准事故和超设计基准事故的评价中，对强度、蒸汽氧化性、失水事故（LOCA）时的耐水淬性和LOCA爆裂性进行了检查。

为了评估实施 FeCrAl-ODS 包壳对当前 BWR 的影响，在正常运行条件下的分析研究中评估了堆芯特性和燃料行为。对 9×9 型和 10×10 型燃料组件和先进 BWR（ABWR）反应堆类型的分析表明 FeCrAl-ODS 燃料包壳具有良好的适用性。

最后，强调了该计划中发现的挑战和前景，以加强国际合作，以促进 FeCrAl-ODS 燃料包壳的发展。