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中国氦冷却固态增殖剂实验包层热工设计 被引量:2

Thermo-hydraulic design of Chinese helium cooled solid breeder blanket for ITER-TBM
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摘要 为进一步优化实验包层模块的热工水力性能,分别研究了实验包层模块的两种不同冷却方案在正常和极端两种不同工况下的温度分布。用流体数值分析软件FLUENT模拟了实验包层模块关键部件的实际温度分布状况。 To further optimize thermo-hydraulic capability of HCSB-TBM, two different thermo-hydraulic schemes would be proposed and investigated by relevant calculating and simulating of thermo-dynamics in normal and peak heat flux condition. With computational fluid dynamics (CFD) code FLUENT, the actual temperature distribution of key components of HCSB-TBM is simulated.
出处 《核聚变与等离子体物理》 CAS CSCD 北大核心 2009年第2期152-155,共4页 Nuclear Fusion and Plasma Physics
关键词 国际热核实验堆 实验包层模块 热工水力设计 ITER Test blanket module Thermo-hydraulic design
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参考文献4

  • 1Yuan T, Feng K M, Zhen Z, et al. Preliminary design and analysis of breeding blanket with helium cooled solid breeder for ITER-TBM [C]. 9^th China-Japan Symposium (CJS-9), O15-18C, Oct. 22--26, 2007.
  • 2Feng Kaiming, Zhang Guo-shu, Chen Zhi, et al. Design description document for the Chinese helium cooled solid breeder test blanket module (Version IV) [R]. Southwestern Institute of Physics, 2007.
  • 3Li Z Q, Feng K M, Zhang G S, et al. 3-D neutronics calculation for 2×6 CH HCSB TBM [C]. 9^th China-Japan Symposium (CJS-9), O15-18C, Oct. 22--26, 2007.
  • 4Goodmal J. The Thermo-dynamic and transport properties of helium [R]. GA-A13400, GATechnologies, 1975.

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