Abstract An accurate nuclear reactor model with less statistical uncertainty is not enough to have an accurate assessment of the calculated physical parameter value. It is worthwhile to note that another source of uncertainties originating from nuclear data uncertainties must be quantified. To realize such an assessment, sensitivity and uncertainty analysis based on first-order perturbation theory implemented in the SCALE code system was applied to the IV.N (an optimized one in series of configurations) core configuration of the Algerian light water Nuclear Uranium Reactor (NUR). The impact of nuclear data uncertainties on the effective multiplication factor was analyzed. Criticality calculation was performed by using the KENO V.a Monte Carlo code of the SCALE code system and the ENDF/B libraries with 238 and 252 energy group structures. The results were compared to the available measurement and validated. The accuracy of this criticality calculation was judged sufficient to do a sensitivity and uncertainty calculation for the same model. First, sensitivity and uncertainty calculations were performed using the TSUNAMI3D module of the SCALE code system and ENDF/B-VII.0 library with the covariance data in 44 and 56 energy group structures. Next, the model was updated to the latest library used in SCALE code system version 6.2.3; ENDF/B-VII.1 with 252 energy group and the corresponding 56 group covariance data. The uncertainty results of NUR effective multiplication factor due to uncertainties in nuclear data were determined. The top contributor is ν ‾ (the average number of neutrons per fission) of 235U for all cases. The total uncertainty in k e f f due to uncertainties in the cross-section data was determined to be around 0.84% using 56 group covariance data. This uncertainty was higher than the uncertainty when using 44 group covariance data.

中文翻译：

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NUR研究堆主要物理参数的核数据不确定性传播

摘要 具有较小统计不确定性的准确核反应堆模型不足以对计算出的物理参数值进行准确评估。值得注意的是，必须量化源自核数据不确定性的另一个不确定性来源。为了实现这样的评估，基于在 SCALE 代码系统中实施的一阶微扰理论的灵敏度和不确定性分析被应用于阿尔及利亚轻水核铀反应堆的 IV.N（一系列优化配置）堆芯配置（ NUR）。分析了核数据不确定性对有效倍增因子的影响。临界值计算是通过使用 SCALE 代码系统的 KENO Va Monte Carlo 代码和具有 238 和 252 能群结构的 ENDF/B 库进行的。将结果与可用的测量结果进行比较并进行验证。判断此临界计算的准确性足以对同一模型进行灵敏度和不确定性计算。首先，使用 SCALE 代码系统的 TSUNAMI3D 模块和 ENDF/B-VII.0 库以及 44 和 56 能组结构的协方差数据进行灵敏度和不确定性计算。接下来将模型更新为SCALE代码系统6.2.3版本使用的最新库；ENDF/B-VII.1 具有 252 个能量组和相应的 56 个组协方差数据。由于核数据的不确定性，确定了NUR有效倍增因子的不确定性结果。对于所有情况，最大的贡献者是 ν ‾（每次裂变的平均中子数）为 235U。由于横截面数据的不确定性，keff 的总不确定性被确定为使用 56 个组协方差数据的 0.84% 左右。这种不确定性高于使用 44 组协方差数据时的不确定性。