...
首页> 外文期刊>Thin Solid Films >Design evaluation of the semi-prototype for the ITER blanket first wall qualification
【24h】

Design evaluation of the semi-prototype for the ITER blanket first wall qualification

机译:ITER橡皮布第一壁鉴定的半原型设计评估

获取原文
获取原文并翻译 | 示例
           

摘要

For the second qualification of the First Wall (FW) procurement of the International Thermonuclear Experimental Reactor (ITER), a semi-prototype of the FW has been designed with increased local surface heat flux up to 5 MW/m~2. With the given conditions, the new semi-prototype design was simulated with the commercial CFD code, the ANSYS-11. The results show that the semi-prototype temperature exceeds the melting temperature of Be, and the current design is required to be modified. In order to enhance cooling, a hypervapotron was added in the design and an analysis with the same code was performed. The results show that the temperature with the hypervapotron reduced by around 100 ℃ but it was still higher than the melting temperature of Be. The hypervapotron mock-up was fabricated and tested with a variance of inlet coolant flow rates and heat fluxes of up to 1.75 MW/m~2 using the second Korea Heat Load Test (KoHLT-2) facility, in which heat was loaded by a graphite heater through radiation heating. Wall and coolant temperatures were measured and compared with the simulation results. So far, there is a large difference between the experiments and the simulation, and a next experiment is being prepared.
机译:为了获得国际热核实验反应堆(ITER)第一壁(FW)采购的第二项资格,已设计了半壁式FW原型,其局部表面热通量增加至5 MW / m〜2。在给定条件下,使用商业CFD代码ANSYS-11对新的半原型设计进行了仿真。结果表明,半原型温度超过了Be的熔化温度,需要对当前的设计进行修改。为了增强冷却效果,在设计中添加了超高压釜,并使用相同的代码进行了分析。结果表明,超高压釜的温度降低了100℃左右,但仍高于Be的熔化温度。使用第二个韩国热负荷试验(KoHLT-2)装置制造并在入口冷却剂流量和热通量变化高达1.75 MW / m〜2的情况下制造并测试了超高压釜模型,其中热负荷通过石墨加热器通过辐射加热。测量了壁温和冷却液温度,并将其与模拟结果进行了比较。到目前为止,实验与模拟之间存在很大差异,并且正在准备下一个实验。

著录项

  • 来源
    《Thin Solid Films》 |2010年第22期|p.6676-6681|共6页
  • 作者单位

    Korea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    rnKorea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    rnKorea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    rnKorea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    rnKorea Atomic Energy Research Institute, Daejeon, Republic of Korea;

    rnUlsan National Institute of Science and Technology, Ulsan, Republic of Korea;

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

    ITER; first wall; hypervapotron; ANSYS-11;

    机译:ITER;第一壁超vapotron;ANSYS-11;

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