BEHAVIORS OF MOLYBDENUM IN UO2FUEL MATRIX
BEHAVIORS OF MOLYBDENUM IN UO2FUEL MATRIX
复制标题
UO2 燃料基质中钼的行为
DOI：
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发表时间：
2011
期刊：
影响因子：
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通讯作者：
K. Song
中科院分区：
文献类型：
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作者：
Yeong;Jong;Yang;Soon;K. Song
钼是最丰富的裂变产物，因为它的裂变产额与氙的裂变产额相当，并且它在核燃料化学中具有非常特殊的作用，因为它影响UO_xO燃料的氧势。利用LA-ICP-MS系统测量了燃耗分别为33.3、41.0和57.6 GWd/tU的二氧化铀乏燃料样品中钼的分布，并获得了测量数据的重现性。Mo的分布几乎是恒定的沿着燃料的半径，除了在燃料的周边增加。结果表明，最高燃耗燃料的测量值偏差相对较大，再现性下降。为了解释这一点，钼在UO氧化物基体中的状态及其对UO氧化物氧化行为的影响进行了研究。低重现性的原因是钼的偏析，也观察到钼对氧化的抑制作用。
Molybdenum is the most abundant fission product since its fission yield is equivalent to that of xenon, and it has a very special role in the chemistry of nuclear fuel because it influences the oxygen potential of UO₂ fuel. In this study, the distribution of molybdenum in spent UO2 fuel specimens with 33.3, 41.0 and 57.6 GWd/tU burnup was measured by a LA-ICP-MS system and the reproducibility of the measured data was obtained. The Mo distribution was almost constant along the radius of a fuel except an increase at the periphery of the fuel. It showed a drop in reproducibility with relatively high deviation of measured values for the highest burnup fuel. To explain this, the state of molybdenum in a UO₂ matrix and its effect on the oxidation behavior of UO₂ were investigated. The low reproducibility was explained by the segregation of molybdenum, and the inhibition of oxidation by the molybdenum was also observed.