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CFTER包层第一壁热工水力分析 被引量:1

Thermal-hydraulic analysis of the CFETR blanket first wall
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摘要 简要描述了CFETR氦冷固态增殖包层的结构设计,介绍了包层第一壁的冷却结构。用ANSYS CFX程序对CFETR包层第一壁进行了热工水力分析。研究了如何获得第一壁的最佳出口温度,并保证第一壁结构材料的热负荷承受能力。讨论了通过改变冷却管道粗糙度和优化冷却管道布置两种方法对第一壁结构进行优化。结果表明,优化的冷却回路既满足了材料的许用温度要求,又满足了氦气的出口温度要求。 This article describes the overall design of CFETR helium cooling solid breeding blanket and the cooling structure of the blanket first wall. Thermal-hydraulic analysis of the CFETR blanket first wall was carried out using ANSYS CFX code. Research on how to get the best outlet temperature and satisfy the limit of the first wall material allowable temperature was done. One way is to promote the tube roughness and another way is to optimize the cooling circulation. The results show that the optimization of the cooling loops can satisfy the requirements of the material allowable temperature and the outlet temperature.
出处 《核聚变与等离子体物理》 CAS CSCD 北大核心 2016年第1期65-70,共6页 Nuclear Fusion and Plasma Physics
关键词 CFETR 包层热工水力 CFX CFETR Blanket thermal hydraulic CFX
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  • 1冯开明.ITER实验包层计划综述[J].核聚变与等离子体物理,2006,26(3):161-169. 被引量:52
  • 2Yuan 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.
  • 3Feng 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.
  • 4Li 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.
  • 5Goodmal J. The Thermo-dynamic and transport properties of helium [R]. GA-A13400, GATechnologies, 1975.
  • 6Hermsmeyer S, Gordeev S, Kleefeldt K, et al. Improved helium cooled pebble bed blanket [R]. FZKA 6399, Dec. 1999.
  • 7Feng K M, Zhang G S, Luo D L, et al. Design Description Document for the Chinese Helium Cooled Solid Breeder (CH HCSB) Test Blanket Module [R]. Chengdu: Southwestern Institute of Physics, 2006.
  • 8TBWG Members. Report from the re-established Test Blanket Working Group for the period of the ITER Transitional Arrangements (ITA)[R]. 2005.
  • 9ITER documents. Structural Design Criteria for ITER In-vessel Components (SDC-IC), Appendix A: Materials design limit data[R]. G 74 MA 8 R0.1, 2004.
  • 10Aiello G, Gabriel F, Giancarli L, et al. Thermal-hydraulic analysis of the HCLL DEMO blanket [J]. Fusion Engineering and Design, 2007, 82: 2189 - 2 194.

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