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Nuclear data for fusion: Validation of typical pre-processing methods for radiation transport calculations

机译:用于核聚变的核数据:辐射传输计算的典型预处理方法的验证

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摘要

Nuclear data form the basis of the radiation transport codes used to design and simulate the behaviour of nuclear facilities, such as the ITER and DEMO fusion reactors. Typically these data and codes are biased towards fission and high-energy physics applications yet are still applied to fusion problems. With increasing interest in fusion applications, the lack of fusion specific codes and relevant data libraries is becoming increasingly apparent. Industry standard radiation transport codes require pre-processing of the evaluated data libraries prior to use in simulation. Historically these methods focus on speed of simulation at the cost of accurate data representation. For legacy applications this has not been a major concern, but current fusion needs differ significantly. Pre-processing reconstructs the differential and double differential interaction cross sections with a coarse binned structure, or more recently as a tabulated cumulative distribution function. This work looks at the validity of applying these processing methods to data used in fusion specific calculations in comparison to fission. The relative effects of applying this pre-processing mechanism, to both fission and fusion relevant reaction channels are demonstrated, and as such the poor representation of these distributions for the fusion energy regime. For the C-nat(n,el) reaction at 2.0 MeV, the binned differential cross section deviates from the original data by 0.6% on average. For the Fe-56(n,el) reaction at 14.1 MeV, the deviation increases to 11.0%. We show how this discrepancy propagates through to varying levels of simulation complexity. Simulations were run with Turnip-MC and the ENDF-B/VII.1 library in an effort to define a new systematic error for this range of applications. Alternative representations of differential and double differential distributions are explored in addition to their impact on computational efficiency and relevant simulation results. (C) 2015 The Authors. Published by Elsevier B.V.
机译:核数据构成了用于设计和模拟ITER和DEMO聚变反应堆等核设施行为的辐射传输规则的基础。通常,这些数据和代码偏向于裂变和高能物理应用,但仍适用于聚变问题。随着人们对融合应用的兴趣日益浓厚,缺乏融合专用代码和相关数据库的情况越来越明显。行业标准的辐射传输代码要求在仿真之前使用预处理的评估数据库。从历史上看,这些方法专注于仿真速度,但要以精确的数据表示为代价。对于遗留应用程序,这并不是主要关注的问题,但是当前的融合需求有很大不同。预处理使用粗糙的装箱结构来重构微分和双微分相互作用的横截面,或者最近将其作为列表的累积分布函数进行重构。与裂变相比,这项工作着眼于将这些处理方法应用于融合特定计算中使用的数据的有效性。证明了将这种预处理机制应用于裂变和聚变相关反应通道的相对效果,因此对于聚变能态,这些分布的表示不佳。对于2.0 MeV的C-nat(n,el)反应,合并的微分截面平均偏离原始数据0.6%。对于在14.1 MeV的Fe-56(n,el)反应,偏差增加到11.0%。我们展示了这种差异如何传播到不同级别的模拟复杂性。使用Turnip-MC和ENDF-B / VII.1库进行了仿真,目的是为此应用定义新的系统错误。除了对计算效率和相关模拟结果的影响外,还探讨了微分和双微分分布的替代表示。 (C)2015作者。由Elsevier B.V.发布

著录项

  • 来源
    《Fusion Engineering and Design》 |2015年第11期|81-86|共6页
  • 作者单位

    Univ Birmingham, Sch Phys & Astron, Birmingham B15 2TT, W Midlands, England|Culham Ctr Fus Energy, Abingdon OX14 3DB, Oxon, England;

    Culham Ctr Fus Energy, Abingdon OX14 3DB, Oxon, England;

    Culham Ctr Fus Energy, Abingdon OX14 3DB, Oxon, England;

    Univ Birmingham, Sch Phys & Astron, Birmingham B15 2TT, W Midlands, England;

  • 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
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