首页> 外文期刊>Fusion Engineering and Design >Experimental and numerical investigations of heat transfer in the first wall of Helium-Cooled-Pebble-Bed Test Blanket Module - Part 1: Presentation of test section and 3D CFD model
【24h】

Experimental and numerical investigations of heat transfer in the first wall of Helium-Cooled-Pebble-Bed Test Blanket Module - Part 1: Presentation of test section and 3D CFD model

机译:氦气卵石床试验毯模块第一壁传热的实验和数值研究-第1部分:试验截面和3D CFD模型的表示

获取原文
获取原文并翻译 | 示例
       

摘要

This paper deals with cooling of the first wall of Helium-Cooled-Pebble-Bed Test Blanket Module (HCPB TBM) for ITER. The first wall cooling is an important investigation issue due to an extreme asymmetry of heat loads: heat flux on the plasma facing side is several times stronger than the one on the side which faces breeding units. Our preliminary 3D CFD analysis revealed that under such conditions the heat transfer coefficient is significantly lower than predicted by common heat transfer correlations (see Ilic et al., 2006). For an experimental validation of these results HETRA (HEat TRAnsfer) test section has been designed and built at the Institute for Neutron Physics and Reactor Technology in Karlsruhe Institute of Technology. The HETRA test section involves in full scale one U-pass of the cooling channel in the first wall of HCPB TBM Version 1.1 (see Meyder et al., 2005). The HCPB TBM relevant experimental conditions have been provided: test channel made of Eurofer steel, helium coolant at pressure of 8 MPa and inlet temperature of 300 ℃ and heat flux of 270 kW/m~2 at the channel surface representing plasma facing side of the first wall. Test channels with hydraulically smooth and with hydraulically rough walls have been built. At each test channel the temperature of Eurofer walls has been measured at ~60 positions. For numerical investigations the 3D CFD modelling with the code STAR CD has been applied. This paper is the first report on this study and presents the development of the test section and of the 3D CFD model. The analyses of the obtained experimental and computational results are presented in the second report (see Ilic et al., 2014).
机译:本文涉及用于ITER的氦冷卵石床测试毯模块(HCPB TBM)的第一壁的冷却。由于热负荷的极端不对称,第一次壁冷却是一个重要的研究问题:面对等离子体的一面的热通量比面对繁殖单元的一面的热通量强几倍。我们的初步3D CFD分析表明,在这种情况下,传热系数明显低于常见的传热相关性所预测的值(请参见Ilic等,2006)。为了对这些结果进行实验验证,在卡尔斯鲁厄技术学院的中子物理和反应堆技术研究所设计并建造了HETRA(HEAT TRAnsfer)测试部分。 HETRA测试部分全面涉及HCPB TBM 1.1版第一壁中冷却通道的一个U型通孔(请参阅Meyder等人,2005)。提供了HCPB TBM的相关实验条件:测试通道由Eurofer钢制成,压力为8 MPa,入口温度为300℃的氦冷却剂,通道表面的热通量为270 kW / m〜2,代表等离子体面向等离子体的一侧。第一堵墙。建造了具有液压光滑壁和液压粗糙壁的测试通道。在每个测试通道上测得的Eurofer壁的温度均在约60个位置。对于数值研究,已使用代码为STAR CD的3D CFD建模。本文是该研究的第一份报告,介绍了测试部分和3D CFD模型的发展。在第二份报告中介绍了对获得的实验和计算结果的分析(请参见Ilic等,2014)。

著录项

  • 来源
    《Fusion Engineering and Design》 |2015年第1期|29-36|共8页
  • 作者单位

    Institute for Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Germany;

    Institute for Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Germany;

    Institute for Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Germany;

    Institute for Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Germany;

    Institute for Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Germany;

    Institute of Nuclear Techniques, Budapest University of Technology and Economics, Hungary;

  • 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
  • 关键词

    Test blanket module; The first wall; Heat transfer; Test section; 3D CFD model;

    机译:测试毯模块;第一堵墙;传播热量;测试部分;3D CFD模型;
  • 入库时间 2022-08-18 00:38:38

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