ABSTRACT In order to evaluate the accuracies of the kinetics parameters predicted with the continuous-energy Monte Carlo calculation code, MVP3, core analysis was performed for light-water moderated UO2 and mixed oxide (MOX) fuel cores for which the ratios of effective delayed-neutron fraction (βeff ) to prompt-neutron life time (ℓ) – represented hereafter by βeff /ℓ – and βeff values were measured. The results obtained with the JENDL-4.0-based neutron library showed that (the calculation values (C)/the measurement values (E)−1) ranged from −1.0% to 4.0% for the βeff /ℓ values with an average of 1.0% and a standard deviation of 1.1% for the 17 cores (the UO2, and UO2-MOX mixed cores) tested in the Tank-Type Critical Assembly (TCA). With respect to the βeff of one UO2 core in TCA, C/E − 1 was 1.2%. For the βeff values of the UO2 and MOX cores tested in the EOLE critical facility, C/E − 1 was −1.5% for the former and −4.6% for the latter. The calculated βeff value of the MOX core using the JEFF-3.2-based neutron library was larger by 4% than that calculated using the JENDL-4.0-based neutron library and showed better agreement to the measurement.

中文翻译：

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应用连续能量蒙特卡罗计算代码 MVP3，分析 TCA 和 EOLE 关键设施的轻水慢化 UO2 和 MOX 核心测量的动力学参数

摘要 为了评估用连续能量蒙特卡罗计算代码 MVP3 预测的动力学参数的准确性，对轻水慢化 UO2 和混合氧化物 (MOX) 燃料芯进行了岩心分析，其有效延迟-中子分数 (βeff) 与瞬发中子寿命 (ℓ) 之间的关系 - 下文用 βeff /ℓ 表示 - 并测量了 βeff 值。使用基于 JENDL-4.0 的中子库获得的结果表明，（计算值（C）/测量值（E）-1）的 βeff /ℓ 值的范围从 -1.0% 到 4.0%，平均值为 1.0在坦克型关键组件 (TCA) 中测试的 17 个岩心（UO2 和 UO2-MOX 混合岩心）的 % 和 1.1% 的标准偏差。对于TCA中一个UO2核的βeff，C/E-1为1.2%。对于在 EOLE 关键设施中测试的 UO2 和 MOX 岩心的 βeff 值，前者的 C/E - 1 为 -1.5%，后者为 -4.6%。使用基于 JEFF-3.2 的中子库计算的 MOX 核心的 βeff 值比使用基于 JENDL-4.0 的中子库计算的值大 4%，并且显示出更好的测量一致性。