Abstract Increasing the fuel burnup limit in light water reactors is sought to enhance fuel cycle economics and requires establishing a technical basis. Experimental observations of severe fuel fragmentation under loss-of-coolant-accident conditions at Halden and Studsvik had raised the need for additional considerations during the development of this technical basis. These test data suggested that the burnup threshold for high burnup fuel fragmentation may be influenced by pre-transient power. Additional loss-of-coolant-accident test data is therefore valuable to complement these tests and enhance the current state of understating. Oak Ridge National Lab has developed the Severe Accident Test Station capable of examining the oxidation kinetics and accident response of irradiated fuel and cladding materials for design basis accident and beyond design basis accident scenarios. Severe Accident Test Station provides various temperature profiles, steam, and the thermal shock conditions necessary for integral loss of coolant accident testing, defueled oxidation quench testing, and high-temperature beyond design basis accident testing. Severe Accident Test Station has been successfully installed and demonstrated in the Irradiated Fuels Examination Laboratory at Oak Ridge National Lab. Furthermore, descriptions of the in-cell re-fabrication capabilities and assembly of the loss-of-coolant-accident test train are provided. Installation of the Severe Accident Test Station system and in-cell re-fabrication restores United States capability to examine postulated and extended loss-of-coolant-accident conditions on spent fuel and cladding and provides a platform for evaluating advanced fuel and accident-tolerant fuel cladding concepts. Lastly, three in-cell integral loss-of-coolant-accident test were performed in the Severe Accident Test Station and compared to the Nuclear Regulatory Commission sponsored loss-of-coolant-accident test as well as the original loss-of-coolant-accident test performed at Argonne National Lab. The results of these tests as well as all publicly available integral loss-of-coolant-accident test were used to validate a threshold for high burnup fuel fragmentation.

中文翻译：

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高燃耗燃料的整体 LOCA 碎裂试验

摘要 提高轻水反应堆的燃料燃耗极限是为了提高燃料循环的经济性，需要建立技术基础。在 Halden 和 Studsvik 的冷却剂损失事故条件下对严重燃料碎裂的实验观察提出了在开发此技术基础期间需要额外考虑的必要性。这些测试数据表明，高燃耗燃料碎片的燃耗阈值可能受瞬态前功率的影响。因此，额外的冷却液损失事故测试数据对于补充这些测试和增强低估的当前状态非常有价值。橡树岭国家实验室开发了严重事故测试站，能够针对设计基准事故和超出设计基准事故场景检查辐照燃料和包壳材料的氧化动力学和事故响应。严重事故测试站提供冷却剂整体损失事故测试、脱燃料氧化淬火测试和超出设计基准的高温事故测试所需的各种温度曲线、蒸汽和热冲击条件。严重事故测试站已在橡树岭国家实验室的辐照燃料检测实验室成功安装和演示。此外，还提供了对冷却液损失事故测试列车的电池内再制造能力和组装的描述。严重事故测试站系统的安装和电池内再制造恢复了美国检查乏燃料和包壳的假设和扩展的冷却剂损失事故条件的能力，并提供了一个评估先进燃料和容灾燃料的平台包层概念。最后，在严重事故试验站进行了三个电池内整体冷却剂损失事故测试，并与核管理委员会赞助的冷却剂损失事故测试以及最初的冷却剂损失试验进行了比较。在阿贡国家实验室进行的事故测试。这些测试的结果以及所有公开可用的整体冷却剂损失事故测试都用于验证高燃耗燃料碎片的阈值。