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Validation of SARAX code system using the SFR operational tests

机译:使用SFR操作测试验证Sarax Code系统

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摘要

This paper introduces extended validation works on SARAX code based on the hot state data of two SFRs, the JOYO and Phenix reactors. Compared with the previous validation based on the zero-power physical tests, these validation cases challenge the code because the calculation should consider more under the operational condition, including the fuel depletion, temperature effect and geometry expansion. Besides, more computational assumptions are discussed in this paper, which contains approximation of constant microscopic cross-sections, sensitivity to different depletion chain and so on. The isothermal temperature effect and burnup reactivity swing calculation were validated using the JOYO reactor and the control rod worth were validated based on the withdrawal tests in the Phenix final tests. The results show that SARAX code has good accuracy in simulating the SFR in the hot states. The neutronic parameters such as reactivity, control rod worth, and power distribution agreed well with the experimental data. (C) 2020 Published by Elsevier Ltd.
机译:本文介绍了基于两个SFR,Joyo和Phenix反应堆的热状态数据的Sarax代码上的扩展验证。与基于零功率物理测试的先前验证相比,这些验证案例挑战代码,因为计算应在操作条件下考虑更多,包括燃料耗尽,温度效应和几何膨胀。此外,本文讨论了更多的计算假设,其含有常数微观横截面的近似,对不同耗尽链的敏感性等。使用Joyo反应器验证等温温度效应和燃烧的反应性摆动计算,并且基于Phenix最终测试中的戒断测试验证了控制杆价值。结果表明,Sarax代码在模拟热状态中的SFR具有良好的准确性。中子参数,如反应性,控制杆价值和配电良好,与实验数据很好。 (c)2020由elestvier有限公司发布

著录项

  • 来源
    《Annals of nuclear energy》 |2020年第11期|107744.1-107744.13|共13页
  • 作者单位

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Xian 710049 Shaanxi Peoples R China|Ulsan Natl Inst Sci & Technol Dept Nucl Engn 50 UNIST Gil Ulsan 44919 South Korea;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Xian 710049 Shaanxi Peoples R China|Xi An Jiao Tong Univ Shaanxi Engn Res Ctr Adv Nucl Energy Xian 710049 Shaanxi Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Xian 710049 Shaanxi Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Xian 710049 Shaanxi Peoples R China|Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Sichuan Peoples R China;

    Xi An Jiao Tong Univ Sch Nucl Sci & Technol Xian 710049 Shaanxi Peoples R China|Nucl Power Inst China Reactor Engn Res Div Chengdu 610213 Peoples R China;

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

    Fast reactor; Validation; Operational tests; Depletion calculation; Temperature effect;

    机译:快速反应堆;验证;操作试验;耗尽计算;温度效应;

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