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REPRESENTABILITY EVALUATION OF FUEL DEBRIS NUCLEAR CHARACTERISTICS BY HETEROGENEOUS CORE OF STACY

机译:异构核的燃料碎片核特征的可代表性评价

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Decommissioning is underway in the Fukushima Daiichi Nuclear Power Station (1FNPS). Criticality control is one of the important safety issues in the decommissioning, especially during fuel debris removal. In 1FNPS, part of fuel debris might be in the form of molten-core-concrete-interaction (MCCI) product. It has been shown that the MCCI product can be critical not only under water but even with water bound in concrete. Further study of criticality characteristics by computation is being conducted to clarify its criticality risk. Furthermore, the risk assessment by computation needs validation by experiment. Japan Atomic Energy Agency is preparing critical experiments with simulated fuel debris in the Static Experiment Critical Facility (STACY), whose solution core will be converted into a new core using fuel rods and light-water moderator. It is difficult to build core configurations composed of water and fuel rods which contain homogeneous mixtures of uranium dioxide (UO_2) and structural materials of boiling light water reactors. In the modified STACY, it is being planned to simulate fuel debris by arranging UO_2 fuel rods and structural material rods in water. In this study, difference in heterogeneity between the experimental core and possible fuel debris conditions is evaluated by comparing infinite multiplication factors and neutron energy spectra.
机译:福岛第一核电站(1FNPS)正在进行退役。临界控制是退役过程中的重要安全问题之一,尤其是在清除燃料残渣的过程中。在1FNPS中,部分燃料碎片可能以熔融核芯混凝土相互作用(MCCI)产品的形式出现。已经表明,MCCI产品不仅在水下甚至在混凝土中结合水时都是至关重要的。通过计算对临界特性进行进一步研究,以弄清其临界风险。此外,通过计算进行的风险评估需要通过实验进行验证。日本原子能机构正在静态实验关键设施(STACY)中使用模拟燃料碎片进行关键实验,该解决方案的解决方案核心将使用燃料棒和轻水缓和剂转换为新的核心。很难建立由水和燃料棒组成的堆芯配置,其中包含二氧化铀(UO_2)和沸腾轻水反应堆的结构材料的均匀混合物。在改进的STACY中,计划通过在水中布置UO_2燃料棒和结构材料棒来模拟燃料碎片。在这项研究中,通过比较无限倍增因子和中子能谱来评估实验堆芯和可能的燃料碎片条件之间的异质性差异。

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