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首页> 外文会议>STP 1467; International Symposium on Zirconium in the Nuclear Industry; 20040613-17; Stockholm(SE) >Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior
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Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior

机译：燃耗54-64MWd / kgU的Zircaloy-4 PWR燃料熔覆层的力学性能及其对RIA行为的影响

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摘要

The PROMETRA material testing program is a support program related to the study of high burnup fuel rod behavior under Reactivity Initiated Accidents (RJA) and to the interpretation of the CABRI REP-Na RIA test results. Hoop and axial tensile tests have been performed on fresh and irradiated Zircaloy-4 cladding alloy first at CEA Grenoble hot labs and now at CEA Saclay in order to assess the cladding mechanical behavior during RIA transients. Efforts have been continuously carried out in order to improve the prototipicallity of the tests for RIA studies involving new specimens and new testing techniques. The corrosion level of irradiated specimens reached up to 130 μm of oxide layer thickness. The influence of in-pile oxide layer spallation has also been addressed. High strain-rate material properties of irradiated Zircaloy-4 and the consequences of hydride embrittlement can be derived from the PROMETRA program.
机译：PROMETRA材料测试程序是一项支持程序，与研究在反应性事故（RJA）下的高燃尽燃料棒行为以及对CABRI REP-Na RIA测试结果的解释有关。首先在CEA格勒诺布尔热实验室对现在的和辐照过的Zircaloy-4熔覆合金进行了箍和轴向拉伸试验，目的是评估RIA瞬态过程中熔覆的力学性能。为了提高涉及新样本和新测试技术的RIA研究的测试的标准性，人们一直在不断地努力。辐照样品的腐蚀水平达到了130μm的氧化层厚度。堆中氧化层剥落的影响也已得到解决。可以从PROMETRA程序中得出Zircaloy-4辐照材料的高应变率材料特性以及氢化物脆化的后果。

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