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Reactivity feedback coefficients of a low enriched uranium fuelled material test research reactor at end-of-life

机译:低浓铀燃料试验研究堆寿命终止时的反应性反馈系数

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The reactivity feedback coefficients at end-of-life of a material test reactor fuelled with low enriched uranium fuel were calculated. The reactor used for the study was the IAEA's 10 MW benchmark reactor. Simulations were carried out to calculate the different reactivity feedback coefficients including Doppler feedback coefficient, reactivity coefficient for change of water temperature and reactivity coefficient for change of water density. Nuclear reactor analysis codes including WIMS-D4 and CITATION were employed to carry out these calculations. It was observed that the magnitude of all the reactivity feedback coefficients increased at end of life of the reactor by almost 2-5%.
机译:计算了以低浓铀燃料为燃料的材料试验反应堆寿命终止时的反应性反馈系数。该研究使用的反应堆是国际原子能机构的10兆瓦基准反应堆。通过仿真计算出不同的反应性反馈系数,包括多普勒反馈系数,水温变化的反应系数和水密度变化的反应系数。包括WIMS-D4和CITATION在内的核反应堆分析代码用于进行这些计算。观察到,所有反应性反馈系数的大小在反应器寿命结束时增加了几乎2%至5%。

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