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First-Order Comprehensive Adjoint Sensitivity Analysis Methodology for Critical Points in Coupled Nonlinear Systems. II: Application to a Nuclear Reactor Thermal-Hydraulics Safety Benchmark

机译:耦合非线性系统临界点的一级全面伴随敏感性分析方法。 II:应用于核反应堆热液压安全基准

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摘要

Responses defined at critical points are particularly important for reactor safety analyses and licensing (e.g., the maximum fuel and/or clad temperature). The novel mathematical framework of the first-order comprehensive adjoint sensitivity analysis methodology for critical points (1st-CASAM-CP) is applied in this work to develop a reactor safety thermal-hydraulics benchmark model which admits exact closed-form expressions for the adjoint functions and for the first-order sensitivities of responses defined at critical points (maxima, minima, saddle points) in physical systems characterized by imprecisely known parameters, external and internal boundaries. This benchmark model is designed for verifying the capabilities and accuracies of computational tools for modeling numerically thermal-hydraulics systems. The unique and extensive capabilities of the 1st-CASAM-CP methodology are demonstrated in this work by considering two responses of paramount importance in reactor safety, namely, (i) the maximum rod surface temperature, which occurs at the imprecisely known interface between the subsystem that models the heat conduction inside the heated rod and the subsystem modeling the heat convection process surrounding the rod; and (ii) the maximum temperature inside the heated rod, which has a critical point with two components, one located at a precisely known boundary of the subsystem that models the heat conduction inside the heated rod, while the other component depends on an imprecisely known boundary (i.e., the rod length). The exact analytical expressions developed in this work for the sensitivities of the maximum internal rod temperature and maximum rod surface temperature, as well as for the sensitivities of the locations where these respective maxima occur, provide exact benchmarks for verifying the accuracy of thermal-hydraulics computational tools. The sensitivities of such responses and of their critical points with respect to model parameters enable the quantification of uncertainties induced by uncertainties stemming from the system’s parameters and boundaries in the respective responses and their underlying critical points.
机译:在关键点定义的反应对于反应堆安全分析和许可(例如,最大燃料和/或包层温度)特别重要。对于关键点(第一Casam-CP)的一级全面伴随敏感性分析方法的新数学框架应用于这项工作中,开发反应堆安全热液压基准模型,该模型承认伴随函数的精确闭合表达式对于特征在于不切定地已知的参数,外部和内部边界的物理系统中的关键点(Maxima,Minima,马鞍点)定义的一阶灵敏度。该基准模型旨在验证计算工具的功能和准确性,用于建模数字热液压系统。在这项工作中,考虑到最重要的反应器安全性的两个反应,即(i)在子系统之间的不精确已知界面发生的最大杆表面温度,通过考虑两个响应,在这项工作中进行了唯一和广泛的曲线方法将加热棒内的导热器和子系统塑造围绕杆围绕的热对流过程模型; (ii)(ii)加热棒内的最大温度,其具有两个部件的临界点,位于子系统的精确已知的边界,其模拟加热棒内的导热,而另一个部件取决于不切实宜的已知边界(即,杆长度)。在这项工作中开发的精确分析表达式对于最大内棒温度和最大杆表面温度的敏感性,以及这些相应的最大值发生的位置的灵敏度提供了精确的基准,用于验证热液压计算的准确性工具。这种响应和它们关键点相对于模型参数的敏感性能够量化由于在各个响应中的系统的参数和边界中源于系统的参数和边界的不确定性而引起的不确定性。

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  • 作者

    Dan Gabriel Cacuci;

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  • 年度 2021
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  • 原文格式 PDF
  • 正文语种 eng
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