期刊文献+

DEMO堆包层第一壁热工水力优化分析研究

Optimization of analysis of DEMO-HCSB first wall based on thermal-hydraulic
下载PDF
导出
摘要 聚变堆包层第一壁是影响包层换热效率与运行安全性最重要的部件,为了研究第DEMO堆包层第一壁的热工水力性能,对第一壁流道内氦气冷却剂的流动及其与结构材料的换热进行了数值模拟研究及优化分析。结果表明,通过增大氦气进口质量流量可以有效地降低第一壁结构材料的最高温度,但是由此带来的压力损失很大,不能作为强化换热的主要途径。此外,增加每组流道的盘绕次数能起到强化换热的效果,目前每组流道盘绕五次的方案是合理的。流道中存在的圆角包层第一壁的流动换热影响不大,但圆角的存在会使第一壁最高温度有一定的升高。铍涂层的导热系数与第一壁最高温度成反相关关系,但是对第一壁流道的对流换热影响不大。结构材料的导热系数的增大能显著降低第一壁结构材料的最高温度。 The first wall(FW) of fusion reactor blanket is an important component to the heat transfer efficiency and operational safety of the reactor.Therefore,thermalhydraulic performance of the FW in DEMO-HCSB is simulated and optimization analysis is conducted using the general purpose computational fluid dynamics(CFD) code FLUENT.By increasing the mass flow of inlet helium,the maximum temperature of structure material of FW reduces significantly while the pressure drop of the helium increases rapidly.It enhances heat transfer performance of FW that increasing the frequency of channel passing through FW in each circuit.There is little influence on thermal-hydraulic performance of FW when it comes to the 3 mm fillet of channel while the maximum temperature of structure material of FW increases with the fillet.The higher thermal conductivity of Beryllium armor leads the lower maximum temperature,which has little influence on the thermal-hydraulic performances of FW.By increasing the thermal conductivity of the structural material can significantly reduce the maximum temperature of the FW.
出处 《核科学与工程》 CAS CSCD 北大核心 2016年第3期347-353,共7页 Nuclear Science and Engineering
基金 磁约束聚变堆若干相关工程技术研究(2011GB113002)
关键词 示范堆 第一壁 热工水力 优化分析 数值模拟 DEMO first wall thermal-hydraulic optimization analysis numerical simulation
  • 相关文献

参考文献8

二级参考文献144

  • 1黄群英,郁金南,万发荣,李建刚,吴宜灿.聚变堆低活化马氏体钢的发展[J].核科学与工程,2004,24(1):56-64. 被引量:88
  • 2吴宜灿,汪卫华,刘松林,黄群英,郑善良,王红艳,陈红丽,陈明亮,柏云清,宋勇,章毛连,柯严,李春京,李艳芬,胡丽琴,刘萍,李静惊,李莹,许德政,曾勤,陈义学.ITER中国液态锂铅实验包层模块设计研究与实验策略[J].核科学与工程,2005,25(4):347-360. 被引量:47
  • 3陈晓军,王和义,罗阳明,冯开明,温兆银.CH HCSB TBM中固体氚陶瓷增殖剂微球研究进展[J].核聚变与等离子体物理,2006,26(3):210-216. 被引量:20
  • 4符晓铭,王捷.高温气冷堆在我国的发展综述[J].现代电力,2006,23(5):70-75. 被引量:30
  • 5黄群英,李春京,李艳芬,刘少军,吴宜灿,李建刚,万发荣,巨新,单以银,郁金南,朱升云,张品源,杨建锋,韩福生,孔明光,李合琴,室贺健夫,长坂琢也.中国低活化马氏体钢CLAM研究进展[J].核科学与工程,2007,27(1):41-50. 被引量:97
  • 6Liu H, et al. Microstructure characterization of oxidation of aluminized coating prepared by a combined process[J]. J Nucl Mater , 2008, 378: 134-138.
  • 7Wang P, et al. Investigation of SiC films deposited onto stainless steel and their retarding effects on tritium per meation[J]. Surf Coat Technol, 2000, 128-129: 99- 104.
  • 8Youngblood G E , et al. SiCf/SiC design for a flow channel insert[R]. Pacific Northwest National Laboratory (PNNL), Department of Energy by Battelle Memorial Institute under contract DE-AC06-76RLO-1830.
  • 9Chuyanov V A , ITER Test Blanket Working Group. ITER Test Blanket Working Group activities: a summary, recommendations and conclusions[J]. Fusion Eng Des, 2002, 61-62:273-281.
  • 10Minutes of the 17th Meeting of the TBWG (TBWG-17) JWS/Cadarache, April 4-6th, 2006. https: //user. iter. org.

共引文献44

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部