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Evaluations of LEU Conversion Impact on the High Temperature Experiment Performance at the MIT Reactor

机译:LEU转化率对MIT反应器高温实验性能的影响评估

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The LEU conversion impact on the high temperature experiment performance at the MIT Reactor has been investigated in this study, with focuses being placed on reactivity worth and nuclear heating capability. The major conclusions can be summarized as follows: 1. The reactivity penalty of the HTIF experiment is less significant in the LEU core than that in the HEU core by ~ 30%, due to the harder neutron spectrum in the former. This implies a generally larger reactivity margin for in-core experiments with use of LEU fuel. 2. The overall impact on the HTIF nuclear heating due to LEU conversion is a 14% reduction, since U-Mo (LEU) fuel is more dense than U-Alx (HEU) fuel. This is because the gamma attenuation effect in the former is significantly stronger. 3. Based on thermal analysis, the average and maximum HTIF temperature in the 7 MW LEU core is lower than that in the 6 MW HEU core by no more than 50℃. This implies that the nuclear heating capability influence on the high temperature experiment performance is insignificant. 4. Compensating the reduced nuclear heating may be feasible by adding irradiation materials (e.g. by increasing the size of tungsten sample holder), since there is sufficient reactivity margin with LEU fuel as compared with that of the reference HEU core.
机译:在这项研究中,研究了低浓铀转化对麻省理工学院反应堆高温实验性能的影响,重点是反应活性值和核加热能力。主要结论可归纳如下:1. HTIF实验的反应性损失在LEU核中不如在HEU核中大30%,这是由于前者的中子光谱较硬。这意味着使用LEU燃料进行的堆芯实验的反应性裕度通常更大。 2.由于低浓铀转化对HTIF核加热的总体影响减少了14%,因为U-Mo(LEU)燃料比U-Alx(HEU)燃料密度更高。这是因为前者的伽马衰减作用明显更强。 3.根据热分析,7 MW LEU堆芯的最高和最高HTIF温度比6 MW HEU堆芯的最高和最高温度低50℃。这表明核加热能力对高温实验性能的影响不明显。 4.通过添加辐射材料(例如,通过增加钨样品架的尺寸)来补偿减少的核加热是可行的,因为与参考HEU堆芯相比,LEU燃料具有足够的反应余量。

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