摘要
为保障第一壁板铍/铜连接的性能满足ITER运行要求,需通过高热负荷疲劳试验评估缺陷的影响,确定可接受的缺陷尺寸、形状、位置等。针对该试验用增强热负荷(EHF)第一壁小模块,通过温度场及弹塑性结构分析,研究试验工况下铍/铜界面预制人工缺陷对模块性能的影响。分析结果表明,缺陷位置和尺寸都会对缺陷附近的弹塑性应变产生直接影响,从而影响模块的热疲劳性能;缺陷越大,影响范围越大;边缘型缺陷的影响远大于中心位置缺陷。
In order to guarantee the performance of the first wall beryllium copper connection under the ITER operation, the high heat flux test(HHFT) should be taken to evaluate the effects of defects, and then determine the acceptable defect size. Aiming at such test, using enhanced heat load(EHF) first wall small module, the temperature field and elastic-plastic structural analysis have been taken to study the effects of Be/Cu Cr Zr interface defects under the high heat flux test condition. Analysis results show that the location and the size of Be/Cu Cr Zr interface defects have a direct impact on local elastic-plastic strain, which affects thermal fatigue performance of the module; the bigger the defects, the greater the influence; marginal type defects is greater than the influence of the center type defects.
引文
[1]Takeshi Hirai,Koichiro Ezato,Patrick Majerus.ITER relevant high heat flux testing on plasma facing surfaces[J].Materials Transactions,2005,46(3):412.
[2]赵周,冯开明,张国书,等.中国ITER固态增殖剂实验包层模块第一壁瞬态热分析[J].核聚变与等离子体物理,2009,29(4):348-352.
[3]贾文宝,黑大千,钱仲悠.聚变堆实验包层模块第一壁温度场及热结构分析[J].原子能科学技术,2010,44(b09):340-345.
[4]康伟山,张斧,吴继红,等.ITER屏蔽包层模块的热工水力与热应力分析[J].核聚变与等离子体物理,2007,27(4):320-323.
[5]Kang Weishan.Hydraulic and thermal analysis of ITER standard NB blanket module[R].Chengdu:21st IAEA Fusion Energy Conference,2006.
[6]ITER International Team.Summary of material properties for structural analysis of the ITER internal components[R].ITER Design Document,2009.
[7]康伟山,张秀杰,袁涛,等.ITER屏蔽包层最新设计的热工水力和热应力分析[J].核聚变与等离子体物理,2011,31(2):161-166.