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核聚变与等离子体物理 ›› 2014, Vol. 34 ›› Issue (3): 200-206.

• 等离子体物理学 • 上一篇    下一篇

中国 HCCB-TBM 氚增殖球床热工水力学特性数值模拟

汪卫华 ,程德胜 ,冯开明 ,邓海飞   

  1. (1. 陆军军官学院应用物理研究所,合肥 230031 ;2. 核工业西南物理研究院,成都 610041)
  • 收稿日期:2013-11-22 修回日期:2014-07-04 出版日期:2014-09-15 发布日期:2014-09-15
  • 作者简介:汪卫华(1965-) ,男,安徽安庆人,博士,教授,博士研究生导师,主要从事反应堆热工流体实验与数值模拟研究。
  • 基金资助:

    国家磁约束核聚变能发展研究专项(2013GB113004) ;国家自然科学基金项目(91326101)

Numerical simulation on thermal hydraulics characteristics of breeder pebble bed for China HCCB-TBM

WANG Wei-hua  , CHENG De-sheng , FENG Kai-ming , DENG Hai-fei   

  1. (1. Institute of Applied physics, Army Officer Academy, Hefei 230031;2. Southwestern Institute of Physics, Chengdu 610041)
  • Received:2013-11-22 Revised:2014-07-04 Online:2014-09-15 Published:2014-09-15

摘要:

基于 CFD 软件平台,针对中国 HCCB-TBM 氚增殖区球床热工水力学特性开展 3 维数值模拟研究。 依据 ITER 实际运行工况给出吹氚氦气和结构冷却剂氦气在硅酸锂球床内的流动与传热特性,获取球床内详细的 速度分布、温度分布和压力降。计算结果表明:圆球的排列方式影响球床内氦气流场和球床的最高温度;ITER 运行工况下 HCCB-TBM 增殖区硅酸锂小球及其壁面的最高温度不会超过设计温度。研究结果为增殖区热工水力 学方案的设计验证和下一步开展实验提供参考。

关键词: ITER , 实验包层模块, 热工水力学, 球床, 吹扫气

Abstract:

Based on the CFD software platform FLUENT, three-dimensional numerical simulation was carried out for thermal hydraulics characteristics of the breeder zone pebble bed for China helium cooled ceramic breeder-test blanket module (HCCB-TBM). According the actual operating conditions of ITER, such as the nuclear heat distributions in the breeder zone and structure wall, the inlet velocities and temperatures of purge gas helium and coolant helium, the flow field and heat transfer characteristics of the purge gas helium carrying the tritium flowing over the lithium silicate pebble bed were obtained, and the temperature distribution and pressure drop were presented as well. The calculation results show that the permutation mode of the lithium silicate spheres in the pebble bed have an influence on the flow field and the maximum temperature of the pebble-bed. The maximum temperature of the pebble-bed and the structure wall does not exceed the designed temperature under the ITER operating conditions. The results will be benefit for the design verification of the breeder zone thermal hydraulics scheme and improving the following experiments of the purge gas.

Key words: ITER, Test blanket module, Thermal-hydraulics, Pebble bed ;Purge gas

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