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利用热等静压扩散焊接技术制备了国际热核聚变试验反应堆(ITER)偏滤器部件的W/Cu Cr Zr焊接模块,并通过电子束试验装置考察模块的耐热负荷性能。为了进一步的考察模块的耐高热负荷性能,利用ANSYS软件模拟计算了稳态和热筛选条件下模块高热负荷(HHF)试验的温度场。结果表明,HHF试验时,试块的最大温度出现在W表面,且W表面的最高温度随着钨块的厚度和吸收功率密度的增大而升高。三种中间层试块,当W块厚度低于8 mm和吸收功率密度低于8 MW/m2时,Cu Cr Zr合金和W材料的最高温度都满足偏滤器PFC设计许用温度的要求。
The W / Cu Cr Zr welding module of the ITER divertor component of ITER was prepared by hot isostatic pressing diffusion welding. The heat load performance of the module was investigated by means of electron beam tester. In order to further investigate the module’s high heat load performance, the temperature field of the module high heat load (HHF) test under steady state and heat screening conditions was simulated by ANSYS software. The results show that the maximum temperature of the specimen appears on the W surface during the HHF test, and the maximum temperature of the W surface increases with the increase of the thickness of the tungsten and the absorption power density. When the thickness of W block is less than 8 mm and the absorbed power density is lower than 8 MW / m2, the maximum temperature of the Cu Cr Zr alloy and the W material meets the allowable design temperature of the divertor PFC.