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首页> 外文期刊>Progress in Nuclear Energy >Prediction of 3D nuclear reactor's operational parameters from 2D fuel lattice design information: A data mining approach
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Prediction of 3D nuclear reactor's operational parameters from 2D fuel lattice design information: A data mining approach

机译:根据2D燃料晶格设计信息预测3D核反应堆的运行参数:一种数据挖掘方法

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摘要

In this paper the estimation of 3D BWR nuclear reactor parameters starting from 2D data is presented. The 3D parameters are obtained through a steady state simulation of the nuclear reactor's operation, namely; thermal limits and cold shutdown margin. Data mining techniques were applied to build decision trees in order to estimate those 3D reactor parameters. The decision trees were built using local power peaking factor, infinite multiplication factor and relative power values of the fuel lattices calculated at the beginning of its life, the number of fuel pins containing gadolinia, uranium enrichments and gadolinia concentration for pins. Using the CASMO-4/SIMULATE-3 system a total of 18,225 operation cycles were simulated in order to generate the dataset for the construction of decision trees. As a result, it was possible to estimate thermal limits with relative errors lower than 5%. The estimation for cold shutdown margin was lower than 200 pcm. Decision trees use 12, 29, and 36 variables to predict SDM, FLPD and MAPRAT values respectively. Decision trees can estimate those core parameters in 25 s against several hours spent by CMS codes. However, the obtained model is not aimed at replacing core simulators to do fuel reloads licensing. It should be considered instead as a tool for a preliminary and fast assessment in an optimization process. Afterwards, the potential solutions must be reassessed and validated with CMS codes execution. (C) 2016 Elsevier Ltd. All rights reserved.
机译:本文提出了从2D数据开始的3D BWR核反应堆参数估计。 3D参数是通过对核反应堆运行的稳态模拟获得的,即:热极限和冷关断裕度。为了估计那些3D反应堆参数,将数据挖掘技术应用于构建决策树。决策树是使用局部功率峰值因子,无穷倍增因子和在其寿命开始时计算出的燃料晶格的相对功率值,包含氧化ado的燃料销数,铀浓缩和销的氧化g浓度构建的。使用CASMO-4 / SIMULATE-3系统,总共模拟了18,225个操作周期,以生成用于构建决策树的数据集。结果,可以估计相对误差低于5%的热极限。冷停工余量的估算值低于200 pcm。决策树使用12、29和36个变量分别预测SDM,FLPD和MAPRAT值。决策树可以在25秒内估算出这些核心参数,而CMS代码要花费几个小时。但是,所获得的模型并非旨在取代核心模拟器来进行燃料再装载许可。相反,应将其视为优化过程中进行初步和快速评估的工具。之后,必须通过CMS代码执行来重新评估和验证潜在的解决方案。 (C)2016 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2016年第8期|97-106|共10页
  • 作者单位

    Univ Murcia, Dept Informat Engn & Commun, Campus Espinardo, E-30100 Murcia, Spain;

    Inst Nacl Invest Nucl Mexico, Dept Sistemas Nucl, Carr Mexico Toluca S-N, La Marquesa Ocoyoacac, Edo Mexico, Mexico;

    Univ Granada, ETSI Informat & Telecomunicac, CITIC UGR, Dept Comp Sci & AI, C Daniel Saucedo Aranda S-N, E-18014 Granada, Spain;

    Inst Nacl Invest Nucl Mexico, Dept Sistemas Nucl, Carr Mexico Toluca S-N, La Marquesa Ocoyoacac, Edo Mexico, Mexico;

    Inst Nacl Invest Nucl Mexico, Dept Sistemas Nucl, Carr Mexico Toluca S-N, La Marquesa Ocoyoacac, Edo Mexico, Mexico;

    Inst Nacl Invest Nucl Mexico, Dept Sistemas Nucl, Carr Mexico Toluca S-N, La Marquesa Ocoyoacac, Edo Mexico, Mexico;

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

    BWR; Reactor simulation; Data mining;

    机译:BWR;反应器模拟;数据挖掘;

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