事故容错燃料UO2-BeO应用于压水堆燃料组件的中子学分析

Neutronic Analysis for Accident Tolerant Fuel UO2-BeO in Fuel Assembly of Pressurized Water Reactor

  • 摘要: 本文基于中子学角度对典型压水堆中的事故容错燃料UO2-BeO设计进行分析。选取西屋公司的2D燃料组件问题,使用组件计算程序ALPHA对不同体积分数BeO的燃料进行计算。临界及燃耗计算结果表明:在燃料中加入BeO,一方面由于中子吸收,导致反应性惩罚;另一方面由于BeO的慢化作用,导致反应性补偿,两个相反影响相互竞争共同决定UO2-BeO燃料带来的综合效应。由反应性匹配基准可知,适量增加235U富集度对维持反应堆整个运行循环的反应性平衡十分必要,其中基准1相对于基准2和3需对燃料富集度进行较大调整才可满足寿期末得到的kinf与参考组件一致。由反应性扰动分析结果可知,当燃料中加入BeO后,燃料温度系数随BeO体积分数的变化基本保持恒定,慢化剂温度系数降低,空泡系数增高。

     

    Abstract: The accident tolerant fuel UO2-BeO design in the typical pressurized water reactor (PWR) was analyzed from the aspect of neutronics. The 2D fuel assembly problem from Westinghouse was selected and fuel with different BeO volume fractions was investigated by fuel assembly calculation code ALPHA. The results from criticality and burnup calculations show that adding BeO in the fuel leads to reactivity penalty caused by neutron capture while the moderating effect of BeO compensates the reactivity provided by the fuel. Two opposite impacts compete with each other to decide the combined effect brought by the UO2-BeO fuel. The results from enrichment search show that slight increase of enrichment of 235U is needed to maintain the reactivity provided by the whole cycle. The fuel enrichment satisfying the first criterion needs more adjustments to meet the kinf obtained at the end of cycle compared with the second criterion and the third criterion. Reactivity perturbation analysis results show that adding BeO in the fuel caused the fuel temperature coefficient keeps constant with the change of BeO volume fraction, the moderator coefficient becomes less negative and void coefficient becomes more negative.

     

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