ITER偏滤器钨/铜穿管模块的高热负荷测试及事后分析
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摘要
对ITER偏滤器钨/铜穿管模块进行了高热负荷测试。测试结果表明,所有的模块都成功承受住了热负荷测试并满足了IO的要求。在高热负荷测试后,对模块进行了事后分析。发现了钨的纵向开裂和Cu/Cu Cr Zr界面的开焊现象。断口的SEM图像表明,钨的开裂方式为脆性的沿晶开裂。通过金相学分析,发现了钨的再结晶现象和钨表面的再结晶深度。还通过有限元分析软件模拟得到了模块的温度分布,并且与实验观察的再结晶现象能够很好的对应。
High heat flux test of ITER divertor W/Cu monoblock mock-ups were finished. All tested mock-ups successfully withstood the heat cycles above and met the requirements of high heat flux performances specified by IO. After HHF test, the post analysis was performed on tested mock-ups. The results found the debonding of the Cu/Cu Cr Zr interface and the crack of W. The scanning electron microscope(SEM) image of the break shows that intergranular rupture was the main mechanism of the W crack. The recrystallization was observed in the W monoblocks and the recrystallized depth was estimated by metallography analysis. The temperature distribution was also obtained by finite element analysis and a good correspondence with recrystallization observed by experiment was found.
High heat flux test of ITER divertor W/Cu monoblock mock-ups were finished. All tested mock-ups successfully withstood the heat cycles above and met the requirements of high heat flux performances specified by IO. After HHF test, the post analysis was performed on tested mock-ups. The results found the debonding of the Cu/Cu Cr Zr interface and the crack of W. The scanning electron microscope(SEM) image of the break shows that intergranular rupture was the main mechanism of the W crack. The recrystallization was observed in the W monoblocks and the recrystallized depth was estimated by metallography analysis. The temperature distribution was also obtained by finite element analysis and a good correspondence with recrystallization observed by experiment was found.
引文
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[2]Hirai T,Escourbiac F,Carpentier-Chouchana S,et al.ITER full tungsten divertor qualification program and progress[J].Physica Scripta,2014,T159:014006.
[3]Hirai T,Escourbiac F,Carpentier-Chouchana S,et al.ITER tungsten divertor design development and qualification program[J].Fusion Engineering and Design,2013,88:1798–1801.
[4]Ezato K,Suzuki S,Seki Y,et al.Progress of ITER full tungsten divertor technology qualification in Japan[J].Fusion Engineering and Design,2015,98–99:1281–1284.
[5]Gavila P,Riccardi B,Pintsuk G,et al.High heat flux testing of EU tungsten monoblock mock-ups for the ITER divertor[J].Fusion Engineering and Design,2015,98–99:1305–1309.
[6]Kuznetsov V,Gorbenko A,Davydov V,et al.Status of the IDTF high-heat-flux test facility[J].Fusion Engineering and Design,2014,89:955–959.
[7]Gavila P,Riccardi B,Constans S,et al.High heat flux testing of mock-ups for a full tungsten ITER divertor[J].Fusion Engineering and Design,2011,86:1652–1655.
[8]Hirai T,Panayotis S,Barabash V,et al.Use of tungsten material for the ITER divertor[J].Nuclear Materials and Energy,2016,9:616–622.