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Optimization of Fast Critical Experiments to Reduce Nuclear Data Uncertainties in Support of a Fast Burner Reactor Design Concept.

机译：支持快速燃烧堆设计概念的快速关键实验的优化，以减少核数据的不确定性。

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摘要

An optimization technique has been developed to select optimized experimental design specifications to produce data specifically designed to be assimilated to optimize a given reactor concept. Data from the optimized experiment is assimilated to generate posteriori uncertainties on the reactor concept's core attributes from which the design responses are computed. The reactor concept is then optimized with the new data to realize cost savings by reducing margin. The optimization problem iterates until an optimal experiment is found to maximize the savings.;A new generation of innovative nuclear reactor designs, in particular fast neutron spectrum recycle reactors, are being considered for the application of closing the nuclear fuel cycle in the future. Safe and economical design of these reactors will require uncertainty reduction in basic nuclear data which are input to the reactor design. These data uncertainty propagate to design responses which in turn require the reactor designer to incorporate additional safety margin into the design, which often increases the cost of the reactor. Therefore basic nuclear data needs to be improved and this is accomplished through experimentation.;Considering the high cost of nuclear experiments, it is desired to have an optimized experiment which will provide the data needed for uncertainty reduction such that a reactor design concept can meet its target accuracies or to allow savings to be realized by reducing the margin required due to uncertainty propagated from basic nuclear data. However, this optimization is coupled to the reactor design itself because with improved data the reactor concept can be re-optimized itself. It is thus desired to find the experiment that gives the best optimized reactor design.;Methods are first established to model both the reactor concept and the experiment and to efficiently propagate the basic nuclear data uncertainty through these models to outputs. The representativity of the experiment to the design concept is quantitatively determined. A technique is then established to assimilate this data and produce posteriori uncertainties on key attributes and responses of the design concept. Several experiment perturbations based on engineering judgment are used to demonstrate these methods and also serve as an initial generation of the optimization problem.;Finally, an optimization technique is developed which will simultaneously arrive at an optimized experiment to produce an optimized reactor design. Solution of this problem is made possible by the use of the simulated annealing algorithm for solution of optimization problems. The optimization examined in this work is based on maximizing the reactor cost savings associated with the modified design made possible by using the design margin gained through reduced basic nuclear data uncertainties. Cost values for experiment design specifications and reactor design specifications are established and used to compute a total savings by comparing the posteriori reactor cost to the a priori cost plus the cost of the experiment. The optimized solution arrives at a maximized cost savings.
机译：已经开发出一种优化技术来选择优化的实验设计规范，以产生专门设计用于吸收以优化给定反应堆概念的数据。吸收来自优化实验的数据，以在反应堆概念的核心属性上生成后验不确定性，从中可以计算出设计响应。然后使用新数据优化反应堆概念，以通过减少利润来节省成本。反复进行优化问题，直到找到最佳实验以最大程度地节省费用为止；未来将考虑使用新一代创新核反应堆设计，尤其是快速中子能谱再循环反应堆来关闭核燃料循环。这些反应堆的安全和经济设计将要求减少输入到反应堆设计中的基本核数据的不确定性。这些数据不确定性会传播到设计响应中，这反过来又要求反应堆设计者将额外的安全裕度纳入设计中，这通常会增加反应堆的成本。因此，需要改进基本的核数据，并通过实验来完成。；考虑到核试验的高成本，希望有一个优化的实验，该实验将提供减少不确定性所需的数据，从而使反应堆设计概念能够满足其要求。目标精度或通过减少由于基本核数据传播的不确定性而需要的裕度来实现节省。但是，这种优化与反应堆设计本身相关，因为有了改进的数据，反应堆概念便可以重新优化。因此，期望找到能够提供最佳优化反应堆设计的实验。首先建立方法以对反应堆概念和实验进行建模，并通过这些模型有效地将基本核数据不确定性传播至输出。实验对设计概念的代表性是定量确定的。然后建立一种技术来吸收这些数据并在设计概念的关键属性和响应上产生后验不确定性。几种基于工程判断的实验扰动被用来证明这些方法，并且可以作为最优化问题的初始产生。最后，开发了一种优化技术，该技术可以同时进行优化实验以产生优化的反应堆设计。通过使用模拟退火算法解决优化问题，可以解决该问题。在这项工作中检验的最优化是基于最大限度地节省与通过使用通过减少基本核数据不确定性而获得的设计余量而进行的改进设计相关的反应堆成本节省。建立了实验设计规范和反应堆设计规范的成本值，并通过将后验反应堆成本与先验成本加实验成本进行比较，将其用于计算总节省额。优化的解决方案可以最大程度地节省成本。

著录项

  • 作者

    Stover, Tracy E., Jr.;

  • 作者单位

    North Carolina State University.;

  • 授予单位 North Carolina State University.;
  • 学科 Engineering Nuclear.;Physics Radiation.;Energy.
  • 学位 Ph.D.
  • 年度 2011
  • 页码 250 p.
  • 总页数 250
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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