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首页> 外文会议>International high-level radioactive waste management conference >PRA - RADIAL HYDRIDE EMBRITTLEMENT IN SPENT PWR NUCLEAR FUEL CLADDING
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PRA - RADIAL HYDRIDE EMBRITTLEMENT IN SPENT PWR NUCLEAR FUEL CLADDING

机译：PRA-压水堆核燃料包壳中的径向氢化物沉淀

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摘要

The work presented in this paper is part of investigations on the structural integrity of Spent Nuclear Fuel (SNF) casks after long-term storage and subjected to normal or accidental conditions of transport. The main challenge of this assessment is to account for the time dependent material degradation mechanisms of the cask components. A Probabilistic Risk Assessment (PRA) is used for the overall assessment of the structural integrity of the relevant package components. SNF rod cladding is likely to control structural failure due to mechanical loads, which can be accelerated by hydride related material degradation of fuel rods after long-term storage. Due to limited available experimental data, statistical methods are used to predict the fuel rod conditions between beginning of storage and moment of transport. The value of the Rod Internal Pressure (RIP) appears to be a driving force for the hydride-induced embrittlement. RIP examination data and recent simulations point towards relatively low Cladding Hoop Stresses (CHSs) in standard rods during drying procedures. An exemplary PRA of the likelihood of cladding embrittlement due to Radial Hydride Reorientation (RHR) is presented. The preliminary model indicates a relatively low probability of cladding embrittlement for standard fuel rods.
机译：本文介绍的工作是对长期储存并处于正常或意外运输条件下的废核燃料（SNF）桶的结构完整性进行研究的一部分。该评估的主要挑战是要考虑桶组件随时间变化的材料降解机理。概率风险评估（PRA）用于对相关包装组件的结构完整性进行整体评估。 SNF棒熔覆层很可能会控制由于机械载荷引起的结构破坏，而这种破坏可通过长期存储后燃料棒的氢化物相关材料降解而加速。由于可用的实验数据有限，因此使用统计方法来预测存储开始到运输之间的燃料棒状况。杆内压力（RIP）的值似乎是由氢化物引起的脆化的驱动力。 RIP检查数据和最新模拟结果表明，在干燥过程中，标准棒中的包层箍应力（CHS）相对较低。呈现了由于径向氢化物重新定向（RHR）而引起的包壳脆化可能性的示例性PRA。初步模型表明，标准燃料棒的包壳脆化可能性相对较低。

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