利用回溯搜索算法对压水堆堆芯装载模式进行多目标优化

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-10 DOI:10.1016/j.anucene.2024.110843
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引用次数: 0

摘要

本研究通过回溯搜索算法(BSA)对典型压水堆初始堆芯配置的堆芯装载模式进行了优化。多目标拟合函数基于同时实现功率峰值因数(ppf)最小化和循环倍增因子(keff)最大化之间的权衡。中子计算使用 PSU-LEOPARD(宾夕法尼亚州立大学--反应堆设计分析相关操作的终生评估)和 MCRAC(多循环反应堆分析代码)代码进行。PSU-LEOPARD 生成的组件数据已输入 MCRAC,它可计算出具有特定加载模式的所有燃料组件的归一化功率曲线。BSA 通过优化多目标函数生成最佳装载模式。实施 BSA 方案后,第一周期长度略有增加(10.1%)。BSA 在核心装载模式优化问题上表现出快速收敛、高效和稳健的特点。
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Multi-objective optimization of a PWR core loading pattern by backtracking search algorithm

In this study, the core loading pattern of the initial core configuration of a typical Pressurized Water Reactor has been optimized through the Backtracking Search Algorithm (BSA). The multi-objective fitness function is based on a trade-off between minimization of the power peaking factor (ppf) and maximization of the cycle multiplication factor (keff) simultaneously. Neutronic computations are performed using the PSU-LEOPARD (Pennsylvania State University-Lifetime Evaluating Operations Pertinent to the Analysis of Reactor Design) and MCRAC (Multiple Cycle Reactor Analysis Code) codes. The PSU-LEOPARD generated assembly data have been fed to MCRAC and it calculates normalized power profiles for all fuel assemblies with a specific loading pattern. The BSA generates best loading patterns by optimizing the multi-objective function. The implementation of the BSA scheme resulted in slight enhancements in the first cycle length (∼10.1 %). The BSA demonstrates rapid convergence, high efficiency and robustness for the core loading pattern optimization problem.

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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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