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Large-Scale Application of the Constraint Annealing Method for Pressurized Water Reactor Core Design Optimization

机译:约束退火方法在压水堆堆芯设计优化中的大规模应用

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摘要

The constraint annealing method is presented and demonstrated for the solution of large-scale, multiconstrained problems in light water reactor fuel cycle optimization. Constraint annealing is a penalty-free method that eliminates the need for traditional constraint weighting factors by treating each objective function and constraint as separate and concurrently solved minimization problems within a global optimization search framework. The current application seeks to demonstrate the effectiveness of constraint annealing for a complex core loading pattern design problem containing multiple objective functions and constraints without the need for additional ad hoc control parameters. Two problems of varying degrees of complexity are analyzed. The first problem is defined by a single objective function based on maximizing cycle energy with two constraints based on power peaking and peak rod exposure. The second problem expands upon the first by adding an additional objective function for vessel fluence and four additional constraints based on controlled power peaking, steaming rate, moderator temperature coefficient, and alternate source term. Results demonstrate that constraint annealing inherently addresses issues of scaling associated with different objective function and constraint formulations as well as the impact on cycle energy.
机译:提出并证明了约束退火方法,用于解决轻水反应堆燃料循环优化中的大规模,多约束问题。约束退火是一种无损失的方法,该方法通过将每个目标函数和约束视为全局优化搜索框架中单独且同时解决的最小化问题,从而消除了对传统约束加权因子的需求。本申请试图证明约束退火对于包含多个目标函数和约束的复杂堆芯加载模式设计问题的有效性,而无需额外的临时控制参数。分析了不同程度的复杂性的两个问题。第一个问题是由一个单一目标函数定义的,该函数基于最大化循环能量并基于功率峰值和峰值棒暴露两个约束。第二个问题是在第一个问题上扩展的,它添加了一个用于容器通量的附加目标函数和四个基于控制功率峰值,汽化速率,调节剂温度系数和备用源项的附加约束。结果表明,约束退火本质上解决了与不同目标函数和约束公式相关的缩放问题,以及对循环能量的影响。

著录项

  • 来源
    《Nuclear science and engineering》 |2019年第5期|523-536|共14页
  • 作者单位

    North Carolina State Univ, Dept Nucl Engn, POB 7909, Raleigh, NC 27695 USA|Oak Ridge Natl Lab, Oak Ridge, TN 37830 USA;

    North Carolina State Univ, Dept Nucl Engn, POB 7909, Raleigh, NC 27695 USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Pressurized water reactor; core design; optimization;

    机译:压水堆;堆芯设计;优化;

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