福岛核电站燃料碎片自然屏障处理临界研究

T. Shimada, K. Takubo, S. Takeda, Tetsuji Yamaguchi
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摘要

未来,在从福岛第一核电站(1F)反应堆安全壳中取出燃料碎片并收集到容器中后,这些容器可能会在一个深层地质储存库中处置。燃料碎片的铀库存和可裂变铀浓缩可高于乏燃料和高水平玻璃化废物的铀库存和铀浓缩。在本研究中,我们利用一维迁移分析估算了天然屏障中铀的析出量,并研究了天然屏障中铀的析出量纲并进行了临界分析。因此,在天然屏障的氧化还原前沿沉淀了200多个MTU,达到临界。临界分析表明,当250 MTU的铀全部以长方体形式分布在累积区大于700 m时,keff小于0.98。
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Study on criticality in natural barrier for disposal of fuel debris from Fukushima Daiichi NPS
After fuel debris is removed from the reactor containment vessel at Fukushima Daiichi NPS (1F) and collected in containers in the future, the containers may be disposed of at a deep geological repository. The uranium inventory and fissile U enrichment of the fuel debris can be higher than those of spent fuels and high-level vitrified wastes. In this study, we estimated the quantity of uranium precipitated at the natural barrier using one-dimensional migration analysis, and studied dimension of uranium precipitated in the natural barrier and carried out the criticality analysis. As the result, more than 200 MTU is precipitated at redox front in the natural barrier to reach the criticality. Criticality analysis indicated that keff is lower than 0.98 when all uranium of 250 MTU distributed into longer than 700 m as cuboid shape at the accumulated area.
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