OECD/NEA反应堆物理基准的四阶伴随灵敏度分析:II。计算四阶灵敏度的数学表达式和cpu时间比较

D. Cacuci, R. Fang
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引用次数: 6

摘要

这项工作扩展到先前发表的关于开发聚乙烯反射钚(首字母缩写:PERP) OECD/NEA反应堆物理基准数值模型的伴随灵敏度和不确定性分析的四阶工作。PERP基准包括7477个不精确已知(不确定)模型参数,这些参数具有非零值。这些参数如下:180个微观总截面;7101显微散射切片;60个微观裂变截面;60个参数表征每次裂变的平均中子数;表征裂变谱的60个参数;表征裂变源的10个参数;还有6个参数表征同位素数密度。先前的研究使用伴随灵敏度分析方法精确有效地计算了PERP基准泄漏响应对所有基准不确定参数的7477个一阶灵敏度和27,956,503个二阶灵敏度。这些研究表明,最大的响应灵敏度涉及总微观截面,这促使最近计算PERP泄漏响应的所有(180)3个三阶灵敏度。结果表明,其中一些三阶截面远远大于相应的二阶截面,因此对PERP基准响应中引起的不确定性影响最大。这一发现推动了本工作中提出的原始四阶公式的发展,这些公式不仅适用于PERP基准,而且可用于计算任何涉及裂变材料和内部或外部中子源的核系统的四阶响应灵敏度。后续的工作将使用本工作中获得的基于伴随的数学表达式来精确有效地计算PERP基准对总微观截面响应的最大四阶灵敏度的数值,并将其用于开创性的PERP基准响应的四阶不确定性分析。
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Fourth-Order Adjoint Sensitivity Analysis of an OECD/NEA Reactor Physics Benchmark: II. Mathematical Expressions and CPU-Time Comparisons for Computing 4th-Order Sensitivities
This work extends to fourth-order previously published work on developing the adjoint sensitivity and uncertainty analysis of the numerical model of a polyethylene-reflected plutonium (acronym: PERP) OECD/NEA reactor physics benchmark. The PERP benchmark comprises 7477 imprecisely known (uncertain) model parameters which have nonzero values. These parameters are as follows: 180 microscopic total cross sections; 7101 microscopic scattering sections; 60 microscopic fission cross sections; 60 parameters that characterize the average number of neutrons per fission; 60 parameters that characterize the fission spectrum; 10 parameters that characterize the fission source; and 6 parameters that characterize the isotope number densities. Previous works have used the adjoint sensitivity analysis methodology to compute exactly and efficiently all of the 7477 first-order and 27,956,503 second-order sensitivities of the PERP benchmark’s leakage response to all of the benchmark’s uncertain parameters. These works showed that largest response sensitivities involve the total microscopic cross sections, which motivated the recent computation of all of the (180)3 third-order sensitivities of the PERP leakage response with respect to these total microscopic cross sections. It turned out that some of these 3rd-order cross sections were far larger than the corresponding 2nd-order ones, thereby having the largest impact on the uncertainties induced in the PERP benchmark’s response. This finding has motivated the development of the original 4th-order formulas presented in this work, which are valid not only for the PERP benchmark but can also be used for computing the 4th-order sensitivities of response of any nuclear system involving fissionable material and internal or external neutron sources. Subsequent works will use the adjoint-based mathematical expressions obtained in this work to compute exactly and efficiently the numerical values of the largest fourth-order sensitivities of the PERP benchmark’s response to the total microscopic cross section and use them for a pioneering fourth-order uncertainty analysis of the PERP benchmark’s response.
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