导线
材料科学
热核聚变
环形场
极限抗拉强度
产量(工程)
管(容器)
复合材料
环面
核工程
等离子体
核物理学
物理
工程类
作者
Zhixiong Wu,Laifeng Li,Chuanjun Huang,Rongjin Huang,Shanfeng Li,Jinggang Qin,Huajun Liu,Yu Wu
标识
DOI:10.1016/j.fusengdes.2013.04.039
摘要
316LN stainless steel is selected as a material for toroidal-field (TF) conductor jacket of International Thermonuclear Experimental Reactor (ITER). In order to evaluate the true mechanical performance of the jacket material at 4.2 K and its suitability as the ITER TF conductor jacket, the mechanical properties of the full-size TF conductor jacket tube and sub-size specimens at 4.2 K and 300 K were investigated according to ASTM standards. The measured yield strength and elongation at 4.2 K for sub-size specimens and full-size tubes are more than 950 MPa and 20%, respectively. In addition, the fractographies of all fractured specimens were observed using scanning electron microscope (SEM). These results suggest that the TF conductor jacket can satisfy ITER requirements and the result of the full-size tube at 4.2 K is more representative and important for practical applications.
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