...
首页> 外文期刊>Nuclear engineering and technology >NUCLEAR DATA UNCERTAINTY AND SENSITIVITY ANALYSIS WITH XSUSA FOR FUEL ASSEMBLY DEPLETION CALCULATIONS
【24h】

NUCLEAR DATA UNCERTAINTY AND SENSITIVITY ANALYSIS WITH XSUSA FOR FUEL ASSEMBLY DEPLETION CALCULATIONS

机译:用XSUSA进行核素数据不确定性和敏感性分析的燃料组装损耗计算

获取原文
获取原文并翻译 | 示例
           

摘要

Uncertainty and sensitivity analyses with respect to nuclear data are performed with depletion calculations for BWR and PWR fuel assemblies specified in the framework of the UAM-LWR Benchmark Phase Ⅱ. For this, the GRS sampling based tool XSUSA is employed together with the TRITON depletion sequences from the SCALE 6.1 code system. Uncertainties for multiplication factors and nuclide inventories are determined, as well as the main contributors to these result uncertainties by calculating importance indicators. The corresponding neutron transport calculations are performed with the deterministic discrete-ordinates code NEWT. In addition, the Monte Carlo code KENO in multi-group mode is used to demonstrate a method with which the number of neutron histories per calculation run can be substantially reduced as compared to that in a calculation for the nominal case without uncertainties, while uncertainties and sensitivities are obtained with almost the same accuracy.
机译:关于核数据的不确定性和敏感性分析,是根据UAM-LWR基准阶段Ⅱ框架中规定的BWR和PWR燃料组件的损耗计算进行的。为此,将基于GRS采样的工具XSUSA与来自SCALE 6.1代码系统的TRITON耗尽序列一起使用。通过计算重要性指标,确定了乘积因子和核素清单的不确定性,以及导致这些结果不确定性的主要因素。使用确定性离散坐标代码NEWT执行相应的中子输运计算。此外,多组模式下的蒙特卡罗代码KENO用于演示一种方法,与没有不确定性,不确定性和不确定性的名义情况下的计算相比,可以大大减少每次计算的中子历史数量。灵敏度几乎以相同的精度获得。

著录项

  • 来源
    《Nuclear engineering and technology》 |2014年第3期|343-352|共10页
  • 作者单位

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH Forschungszentrum, Boltzmannstrasse 14, 85748 Garching, Germany;

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH Forschungszentrum, Boltzmannstrasse 14, 85748 Garching, Germany;

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH Forschungszentrum, Boltzmannstrasse 14, 85748 Garching, Germany;

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH Forschungszentrum, Boltzmannstrasse 14, 85748 Garching, Germany;

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH Forschungszentrum, Boltzmannstrasse 14, 85748 Garching, Germany;

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH Forschungszentrum, Boltzmannstrasse 14, 85748 Garching, Germany;

    Department of Nuclear Engineering, Universidad Politecnica de Madrid, c/ Jose Gutierrez Abascal, 2, 28026 Madrid Spain;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Uncertainty/sensitivity Analysis; Random Sampling; Fuel Assembly Depletion; UAM-LWR Benchmark; XSUSA; SCALE; Fast GRS Method;

    机译:不确定度/敏感性分析;随机抽样燃料组件耗竭;UAM-LWR基准;XSUSA;规模;快速GRS方法;

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号