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首页> 外文期刊>Nuclear science and engineering >Steady-State Thermal-Hydraulic Analysis of the Oregon State University TRIGA Reactor Using RELAP5-3D
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Steady-State Thermal-Hydraulic Analysis of the Oregon State University TRIGA Reactor Using RELAP5-3D

机译:使用RELAP5-3D对俄勒冈州立大学TRIGA反应堆进行稳态热工水力分析

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摘要

Oregon State University has recently conducted a complete core conversion analysis as part of the Reduced Enrichment for Research and Test Reactors Program. The goals of the thermal-hydraulic steady-state analysis were to calculate natural-circulation flow rates, coolant temperatures, and fuel temperatures as a function of core power, as well as peak values of fuel temperature, cladding temperature, surface heat flux, critical heat flux ratio, and temperature profiles in the hot channel for both the highly enriched uranium and low-enriched uranium cores.rnRELAP5-3D Version 2.4.2 was used for all computational modeling during the thermal-hydraulic analysis. This is a lumped parameter code forcing engineering assumptions to be made during the analysis. A single-hot-channel model's results are compared to results produced from more refined two- and eight-channel models in order to identify variations in thermal-hydraulic characteristics as a function of spatial refinement.
机译:俄勒冈州立大学最近进行了完整的岩心转化分析,作为“研究与测试反应堆减少浓缩”计划的一部分。热工液压稳态分析的目标是计算自然循环流量,冷却液温度和燃料温度,这些功率是核心功率的函数,以及燃料温度,包层温度,表面热通量,临界值的峰值高浓缩铀芯和低浓缩铀芯的热通量比和热通道中的温度曲线。rnRELAP5-3D版本2.4.2用于热工水力分析过程中的所有计算建模。这是一个集总参数代码,在分析过程中必须进行工程假设。将单热通道模型的结果与更精细的二通道和八通道模型产生的结果进行比较,以识别热工液压特性随空间优化的变化。

著录项

  • 来源
    《Nuclear science and engineering》 |2009年第3期|261-274|共14页
  • 作者单位

    Oregon State University, Department of Nuclear Engineering 116 Radiation Center, Oregon State University, Corvallis, Oregon 97330;

    Oregon State University, Department of Nuclear Engineering 116 Radiation Center, Oregon State University, Corvallis, Oregon 97330;

    Oregon State University, Department of Nuclear Engineering 116 Radiation Center, Oregon State University, Corvallis, Oregon 97330;

    Oregon State University, Department of Nuclear Engineering 116 Radiation Center, Oregon State University, Corvallis, Oregon 97330;

    Oregon State University, Department of Nuclear Engineering 116 Radiation Center, Oregon State University, Corvallis, Oregon 97330;

    Oregon State University, Department of Nuclear Engineering 116 Radiation Center, Oregon State University, Corvallis, Oregon 97330;

  • 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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