Abstract The void reactivity of a fuel assembly with a streaming channel was measured in a simulated light water reactor critical lattice. The void reactivity was defined as the difference of reactivity ρ between different void conditions. Stainless steel and Zircaloy are candidates for the streaming channel material. Aluminum was used in this measurement because it is inexpensive and its absorption cross section is similar to that of Zircaloy. Two types of streaming channels were used: one made of aluminum and the other made of stainless steel. The two streaming channels were compared in terms of the difference in void reactivity. Measured values were calculated using a continuous-energy Monte Carlo code, MCNP6.1, with the JENDL-4.0 and ENDF/B-VIII.0 nuclear data libraries. The measured values and the calculated values agree within an error range of approximately 10% for the aluminum streaming channel and approximately 20% for the stainless steel streaming channel. The streaming effect of reactivity was deduced from the changes of migration area and buckling, which were measured using the water-height coefficient of reactivity and the axial fission-rate distribution.

中文翻译：

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流道 LWR 临界实验中空隙反应性的流效应

摘要 在模拟轻水反应堆临界晶格中测量了带有流道的燃料组件的空隙反应性。空隙反应性定义为不同空隙条件之间反应性ρ的差异。不锈钢和锆合金是流道材料的候选材料。在此测量中使用铝是因为它价格低廉且其吸收截面与锆合金相似。使用了两种类型的流道：一种由铝制成，另一种由不锈钢制成。根据空隙反应性的差异比较了两个流通道。测量值使用连续能量蒙特卡罗代码 MCNP6.1 和 JENDL-4.0 和 ENDF/B-VIII.0 核数据库计算。测量值和计算值在铝流道约 10% 和不锈钢流道约 20% 的误差范围内一致。利用反应性水高系数和轴向裂变速率分布测量迁移面积和屈曲的变化，推导出反应性的流动效应。