Abstract

In this work, we present our MCNP6.1 modeling of some critical fast experimental benchmarks, aiming to qualify our cross section libraries derived from ENDF/B-VII.1, ENDF/B-VII, JEFF-3.1, JENDL-3.3, and JENDL-4.0. The analyzed benchmarks are characterized by simple geometries which helps to have taken precise results, and concerning the type: HEU-MET-FAST (highly enriched uranium). Those benchmarks are extracted from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (IHECSBE) published by the Nuclear Energy Agency [1]. A detailed comparison of the results of our simulation was made in order to highlight the influence of these nuclear data types on our calculations, due to its importance for the stability of nuclear reactors. We interpreted the difference between calculation and experiment (\(C{-}E\)) for the principal parameter \(k_{\textrm{eff}}\) through a comparison of the fission and capture rates of the major fissile elements. The different spectral indices F28/F25, F49/F25, F37/F25, C28/F25, and F23/F25 at the cores center are also calculated. For the majority of the studied HEU (highly enriched uranium) benchmark cases, The ENDF/B-VII and JEFF-3.1 have a good agreement with the experimental ones, concerning the \(k_{\textrm{eff}}\) results. The average discrepancy from the experimental values for ENDF/B-VII is 0.42\(\%\), and 0.39\(\%\) for JEFF-3.1. An overestimation was observed for most evaluations concerning benchmarks with tungsten carbonate reflectors. The best results were obtained by JENDL-3.3, with a maximal discrepancy \(C{-}E\) estimated 0.47\(\%\) concerning fission rate, and 4.25\(\%\) for capture rate. In analyzing the spectral indices, for GODIVA and FLATTOP-25, the best results were obtained by JENDL-4.0 with a maximal discrepancy of 2.66\(\%\).

中文翻译：

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使用Mcnp6.1代码通过快速基准高浓缩铀研究分析最近的核数据

摘要

在这项工作中，我们介绍了一些关键的快速实验基准的MCNP6.1建模，旨在验证我们从ENDF / B-VII.1，ENDF / B-VII，JEFF-3.1，JENDL-3.3和JENDL-4.0。经分析的基准具有简单的几何形状，有助于获得精确的结果，并涉及以下类型：HEU-MET-FAST（高浓缩铀）。这些基准摘自《国际评估的临界安全性基准实验》（IHECSBE）由核能署[1]出版。由于其对核反应堆稳定性的重要性，因此对我们的模拟结果进行了详细的比较，以突出这些核数据类型对我们的计算的影响。通过比较主要裂变元素的裂变率和捕获率，我们解释了主要参数\（k _ {\ textrm {eff}} \）的计算与实验（\（C {-} E \））之间的差异。还计算了核心中心处的不同光谱指数F28 / F25，F49 / F25，F37 / F25，C28 / F25和F23 / F25。对于大多数研究的HEU（高浓铀）基准案例，ENDF / B-VII和JEFF-3.1与实验性案例在\（k _ {\ textrm {eff}} \）上具有很好的一致性。结果。ENDF / B-VII与实验值的平均差异为0.42 \（\％\），而JEFF-3.1为0.39 \（\％\）。对于大多数有关使用碳酸钨反射镜的基准的评估，都观察到了高估。最好的结果是由JENDL-3.3获得，具有最大差异\（C { - }ë\）估计0.47 \（\％\）关于裂变率，和4.25 \（\％\）用于捕获率。在分析光谱指数时，对于GODIVA和FLATTOP-25，通过JENDL-4.0可获得最佳结果，最大差异为2.66 \（\％\）。