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MOx benchmark calculations by deterministic and Monte Carlo codes

机译:通过确定性代码和蒙特卡洛代码进行MOx基准计算

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摘要

A depletion calculation benchmark devoted to MOx fuel is an ongoing objective of the OECD/NEA WPRS following the study of depletion calculation concerning UOx fuels. The objective of the proposed benchmark is to compare existing depletion calculations obtained with various codes and data libraries applied to fuel and back-end cycle configurations.In the present work the deterministic code NEWT/ORIGEN-S of the SCALE6 codes package and the Monte Carlo based code MONTEBURNS2.0 were used to calculate the masses of inventory isotopes. The methodology to apply the MONTEBURNS2.0 to this benchmark is also presented. Then the results from both code were compared.
机译:在研究了有关UOx燃料的损耗计算之后,专门用于MOx燃料的损耗计算基准是OECD / NEA WPRS的一项持续目标。拟议基准的目的是将现有的耗油量计算与适用于燃油和后端循环配置的各种代码和数据库进行比较。在当前工作中,SCALE6代码包和蒙特卡洛的确定性代码NEWT / ORIGEN-S使用基于代码MONTEBURNS2.0的方法来计算库存同位素的质量。还介绍了将MONTEBURNS2.0应用于该基准的方法。然后比较两个代码的结果。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2012年第5期|p.63-68|共6页
  • 作者单位

    San Piero a Crado Nuclear Research Croup (GRNSPG), University of Pisa, via Diotisalvi2, 56122 Pisa, Italy;

    San Piero a Crado Nuclear Research Croup (GRNSPG), University of Pisa, via Diotisalvi2, 56122 Pisa, Italy;

    San Piero a Crado Nuclear Research Croup (GRNSPG), University of Pisa, via Diotisalvi2, 56122 Pisa, Italy;

    San Piero a Crado Nuclear Research Croup (GRNSPG), University of Pisa, via Diotisalvi2, 56122 Pisa, Italy;

  • 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
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