首页> 外文期刊>Nuclear Engineering and Design >Air ingress benchmarking with computational fluid dynamics analysis
【24h】

Air ingress benchmarking with computational fluid dynamics analysis

机译:带有计算流体动力学分析的进气基准测试

获取原文
获取原文并翻译 | 示例
       

摘要

The air ingress accident is a complicated accident scenario that may limit the deployment of high-temperature gas reactors. The complexity of this accident scenario is compounded by multiple physical phenomena that are involved in the air ingress event. These include diffusion, natural circulation, and complex chemical reactions with graphite and oxygen. In an attempt to better understand the phenomenon, the FLUENT-6 computational fluid dynamics code was used to assess two air ingress experiments. The first was the Japanese series of tests performed in the early 1990s by Takeda and Hishida. These separate effects tests were conducted to understand and model a multi-component experiment in which all three processes were included with the introduction of air in a heated graphite column. MIT used the FLUENT code to benchmark these series of tests with quite good results. These tests are generically applicable to prismatic reactors and the lower reflector regions of pebble-bed reactors. The second series of tests were performed at the NACOK facility for pebble bed reactors as reported by Kuhlmann [Kuhlmann, M.B., 1999. Experiments to investigate flow transfer and graphite corrosion in case of air ingress accidents in a high-temperature reactor]. These tests were aimed at understanding natural circulation of pebble bed reactors by simulating hot and cold legs of these reactors. The FLUENT code was also successfully used to simulate these tests. The results of these benchmarks and the findings will be presented.
机译:进气事故是一个复杂的事故场景,可能会限制高温气体反应堆的部署。进气事件中涉及的多种物理现象使这种事故场景的复杂性更加复杂。其中包括扩散,自然循环以及与石墨和氧气的复杂化学反应。为了更好地理解这种现象,使用了FLUENT-6计算流体动力学代码来评估两个进气实验。首先是1990年代初由武田和Hishida进行的日本系列测试。进行这些单独的效果测试是为了理解和模拟多组分实验,在该实验中,将所有三个过程都包括在加热的石墨塔中引入空气。麻省理工学院使用FLUENT代码对这一系列测试进行基准测试,结果相当不错。这些测试通常适用于棱柱形反应器和卵石床反应器的下部反射器区域。第二系列试验是在NACOK设施的卵石床反应器上进行的,如Kuhlmann所报道[Kuhlmann,M.B.,1999。实验以研究在高温反应器中发生进气事故时的流动和石墨腐蚀]。这些测试旨在通过​​模拟卵石床反应器的热腿和冷腿来理解卵石床反应器的自然循环。 FLUENT代码也已成功用于模拟这些测试。将介绍这些基准测试的结果和调查结果。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2006年第6期|p.587-602|共16页
  • 作者

    Andrew C. Kadak; Tieliang Zhai;

  • 作者单位

    Department of Nuclear Engineering, Massachusetts Institute of Technology, United States;

  • 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 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:46:56

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