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Uncertainty Quantification, Sensitivity Analysis, And Data Assimilation For Nuclearsystems Simulation

机译:核系统仿真的不确定度量化,灵敏度分析和数据同化

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摘要

Reliable evaluation of nuclear data will play a major role in reduction of nuclear systems simulation uncertainties via the use of advanced sensitivity analysis (SA), uncertainty quantification (UQ), and data assimilation (DA) methodologies. This follows since nuclear data have proven to constitute a major source of neutronics uncertainties. This paper will overview the useof the Efficient Subspace Method (ESM), developed at NCSU, to overcome one of the main deficiencies of existing methodologies for SA/UQ/DA, that is the ability to handle codes with large input and output (I/O) data streams, where neither the forward nor the adjoint approach alone are appropriate. We demonstrate the functionality of ESM for an LWR core, a boiling water reactor, and a fast reactor benchmark experiment, the ZPR6/7A assembly. This work demonstrates the capability of adjusting cross section data thereby providing guidance to cross section evaluation efforts by identification of key cross sections and associated energy ranges that contribute the most to the propagated core attributes uncertainties.
机译:通过使用高级敏感性分析(SA),不确定性量化(UQ)和数据同化(DA)方法,对核数据进行可靠的评估将在减少核系统模拟不确定性中发挥重要作用。这是因为核数据已经证明是中子学不确定性的主要来源。本文将概述在NCSU开发的有效子空间方法(ESM)的使用,以克服SA / UQ / DA现有方法的主要缺陷之一,即处理具有大输入和输出代码的能力(I / O)数据流,仅前向方法和伴随方法都不适用。我们演示了LSM堆芯,沸水反应堆和快速反应堆基准试验ZPR6 / 7A组件的ESM功能。这项工作展示了调整横截面数据的能力,从而通过识别关键横截面和相关的能量范围为横截面评估工作提供指导,这些关键横截面和相关的能量范围对传播的核心属性不确定性影响最大。

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