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Neutron Intensity of Fast Reactor Spent Fuel

机译:快堆乏燃料的中子强度

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Neutron intensity of spent fuel of the JOYO Mk_II core with a burnup of 62,500MWd/t and cooling time of 5.2 years was measured at the spent fuel storage pond. The measured data were compared with the claculated values on the JOYO core management code system "MAGI", and the average C/E approximately 1.2 was obtained. It was found that the axial neutron intensity didn't simply follow the burnup distribution, and the neutron intensity was locally increased at the bottom end of the fuel region dueto an accumulation of ~244Cm.
机译:在花费燃料储存池中测量了Joyo MK_II核心的废气的中子强度,燃烧的燃料为62,500MWd / t和5.2岁的冷却时间。将测量的数据与Joyo核心管理代码“MAGI”的碎片值进行比较,并且获得了大约1.2的平均C / E.发现轴向中子强度并不简单地遵循燃烧分布,并且在燃料区的底端底部局部强度在燃料区底部占〜244cm的累积。

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