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首页> 外文期刊>Journal of nuclear science and technology >Effect of pre-hydriding on thermal shock resistance of Zircaloy-4 cladding under simulated loss-of-coolant accident conditions
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Effect of pre-hydriding on thermal shock resistance of Zircaloy-4 cladding under simulated loss-of-coolant accident conditions

机译:模拟失水事故条件下预加氢对Zircaloy-4熔覆层抗热震性的影响

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摘要

Experiments simulating loss-of-coolant accident (LOCA) conditions were performed to evaluate the effect of prehydriding on the thermal-shock resistance of oxidized Zircaloy-4 cladding. Test rods fabricated with 580-mm long claddings were isothermally oxidized at temperatures ranging from 1,220 to 1,530 Kin steam and then were quenched with flooding water. Both artificially hydrided (400 to 600 ppm) and non-hydrided claddings were subjected to these tests. Since cladding fracture on quenching primarily depends on the amount of oxidation, the fracture threshold was evaluated in terms of "equivalent cladding reacted (ECR)." Under an axially unrestrained condition, the fracture threshold is about 56% ECR, and the influence of pre-hydriding is not observed. The fracture threshold is decreased by restraining the test rods on quenching, and it is more remarkable in pre-hydrided claddings than in non-hydrided claddings. Consequently, the fracture threshold was about 20% ECR and 10% ECR for non-hydrided and pre-hydrided claddings, respectively, under the fully restrained condition. These results indicate a possible decrease of fracture threshold of high burn-up fuel claddings under LOCA conditions.
机译:进行了模拟失水事故(LOCA)条件的实验,以评估预氢化对氧化Zircaloy-4覆层的耐热冲击性的影响。用580毫米长的包层制成的测试棒在1,220至1,530 Kin蒸汽的温度下进行等温氧化,然后用注水淬火。人工氢化(400至600 ppm)和非氢化覆层均经过了这些测试。由于淬火时的包层断裂主要取决于氧化量,因此以“反应的等效包层(ECR)”来评估断裂阈值。在轴向不受约束的条件下,断裂阈值约为56%ECR,并且未观察到预氢化的影响。通过限制测试棒的淬火来降低断裂阈值,并且在预水熔覆层中比在非水熔覆层中更明显。因此,在完全约束的情况下,非水合和预水合覆层的断裂阈值分别约为20%ECR和10%ECR。这些结果表明,在LOCA条件下,高燃耗燃料包壳的断裂阈值可能会降低。

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