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基于不同评价核数据库的空间堆临界基准检验研究

Study on Criticality Benchmark Testing in Spatial Reactors Based on Different Evaluated Nuclear Databases

  • 摘要: 为提高空间堆中子学模拟的可靠性,基于国际临界安全手册中关于空间堆的临界基准实验(HMF005基准实验),采用蒙特卡罗程序对HMF005基准实验中堆芯排布进行建模,结合不同评价核数据库,计算6种堆芯排布下的keff计算值与实验值的偏差,并对计算值与实验值的比值的平均值、标准偏差、χ2和均方根误差等进行深入分析。研究发现,ENDF/B-VII.1、CENDL-3.2、ENDF/B-VIII.0和JEFF-3.3四种评价核数据库计算堆芯keff结果与实验值偏差处于3倍不确定度之内,其中ENDF/B-Ⅶ.1计算结果最接近实验值,CENDL-3.2与实验偏差稍大。CENDL-3.2库计算结果与实验值偏差稍大主要是由于评价库中的钼和铍核素导致,钼的同位素中92Mo的影响最大。同时还进行敏感性分析,92Mo和9Be的总反应敏感性系数主要跟弹性散射敏感性系数相关,CENDL-3.2和ENDF/B-Ⅶ.1中的9Be辐射俘获敏感性系数差异较大,两者的偏差可达34.9%。

     

    Abstract: To enhance the reliability of neutronics simulations for space reactors, this study utilized the Monte Carlo code to model the core configuration of the HMF005 critical benchmark experiment (from the International Handbook of Criticality Safety Benchmark Experiments) and evaluated six core configurations using different nuclear data libraries. The deviations between calculated keff values and experimental results were systematically analyzed with statistical evaluations of mean ratios, standard deviations, χ2, and root mean square errors. The results indicate that four evaluated nuclear data libraries-ENDF/B-VII.1, CENDL-3.2, ENDF/B-VIII.0, and JEFF-3.3-yield keff values within three times the experimental uncertainty. Among these, ENDF/B-VII.1 showed the closest agreement with experimental data, while CENDL-3.2 exhibited slightly larger deviations. Further analysis revealed that the discrepancies in CENDL-3.2 primarily stem from molybdenum (Mo) and beryllium (Be) isotopes, with 92Mo contributing most significantly. Sensitivity analysis demonstrated that the total reaction sensitivity coefficients for 92Mo and 9Be are predominantly governed by elastic scattering sensitivities. Notably, a 34.9% discrepancy was observed between the radiative capture sensitivity coefficients of 9Be in CENDL-3.2 and ENDF/B-VII.1.

     

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