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A STYLIZED THREE-DIMENSIONAL PRESSURIZED WATER REACTOR BENCHMARK PROBLEM WITH UO_2 AND MOX FUEL

机译:UO_2和Mox燃料的三维三维加压水反应器基准问题

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摘要

This paper fully describes a whole-core benchmark problem based on a small two-loop pressurized water reactor composed of UO_2 and MOX fuel assemblies. The specification includes heterogeneity at both the assembly and the core levels. The geometry and material compositions are fully described, and multigroup material cross-section libraries are provided in the two-group, four-group, and eight-group formats. Detailed Monte Carlo reference solutions including core eigenvalue, assembly-averaged fission distribution, and selected fuel pin fission density distributions are presented for benchmarking diffusion and transport methods. Three different core configurations are presented in this paper, namely, all-rods-out, all-rods-in, and some-rods-in.
机译:本文充分描述了一个由UO_2和MOX燃料组件组成的小型两回路压水堆的全核基准测试问题。该规范包括组装和核心级别的异质性。完整描述了几何形状和材料成分,并以两组,四组和八组格式提供了多组材料截面库。提出了详细的蒙特卡罗参考解决方案,包括堆芯特征值,组件平均裂变分布和选定的燃料销裂变密度分布,以作为基准扩散和运输方法。本文介绍了三种不同的核心配置,即全杆出,全杆入和某些杆入。

著录项

  • 来源
    《Nuclear Technology》 |2013年第1期|1-28|共28页
  • 作者单位

    Georgia Institute of Technology, Nuclear and Radiological Engineering/ Medical Physics Programs, George W. Woodruff School, Atlanta, Georgia 30332-0405;

    Georgia Institute of Technology, Nuclear and Radiological Engineering/ Medical Physics Programs, George W. Woodruff School, Atlanta, Georgia 30332-0405;

    Georgia Institute of Technology, Nuclear and Radiological Engineering/ Medical Physics Programs, George W. Woodruff School, Atlanta, Georgia 30332-0405;

  • 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

    PWR benchmark problems; neutronicsl whole-core transport;

    机译:压水堆基准问题;neutronicsl全核心运输;

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