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AN ASSESSMENT OF FUEL DAMAGE IN POSTULATED REACTIVITY-INITIATED ACCIDENTS

机译:假定反应性引发的事故中的燃油损害评估

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In late 1993 and early 1994, tests in France and Japan showed that cladding damage in fuel rods with burnups above 50 GWd/ton occurs at much lower energies than in unirradiated fuel rods when exposed to large power pulses. During the last decade, significant additional test results have become available to permit an interim assessment of potential cladding failure in reactivity-initiated accidents (RIAs) in reactors with fuel burnups above 40 GWd/ton, which is generally regarded as high-burnup fuel. These data are summarized, and systematic biases due to atypical test conditions are identified. The magnitude of biases in the fuel enthalpy for failure are estimated to range from -19 to +27 cal/g for the cases analyzed. With these adjustments, a lower bound of the enthalpies for experimentally observed cladding failure is compared with potential enthalpies in pressurized water reactors and boiling water reactors. Based on available information on control rod worths, it is concluded that current operating reactors in the United States are not likely to experience cladding failure during the worst postulated RIAs.
机译:在1993年末和1994年初,在法国和日本进行的测试表明,燃耗超过50 GWd / ton的燃料棒的包层损坏发生在比暴露于大功率脉冲的未辐射燃料棒低得多的能量下。在过去的十年中,已经有了大量的附加测试结果,可以对燃耗超过40 GWd /吨的反应堆(通常被认为是高燃耗燃料)的反应堆引发的事故(RIA)的潜在包壳失效进行临时评估。总结了这些数据,并确定了由于非典型测试条件引起的系统偏差。对于所分析的情况,失效的燃料焓的偏差的大小估计为-19至+27 cal / g。通过这些调整,将实验观察到的熔覆失效的焓下限与压水反应堆和沸水反应堆中的潜在焓进行了比较。根据有关控制棒价值的可用信息,得出的结论是,在假定最差的RIA期间,美国当前运行的反应堆不太可能出现包壳故障。

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