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Specific Features of Electron-Beam Welding of ITER Blanket First Wall Components

机译:电子束焊接浸渍第一壁部件的特殊特征

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Abstract— Specific features of fabricating welded structures of the international thermonuclear experimental reactor (ITER) blanket components are considered. The results from elaborating the technology for electron-beam welding of cooling system’s channel caps in the first wall bearing structure (FWBS) of the ITER blanket shielding module are presented. The design of welded joint samples made of Grade 316L(N) steel and the welding equipment are described. The welding techniques and butt joint design features whose use makes it possible to obtain the required strengthening of weld bead and to avoid metal droplets from appearing in the FWBS inner cavities are considered. A simplified thermal–mechanical model of the cap-welding technological process is described, and the results from experimentally evaluating the structural and mechanical state of the obtained welded structures are presented. A comparison between the modeling and experimental results is given. It is pointed out that the stressed and strain state varies in an active manner at the initial loading stage. Initially, the metal in the heat-affected zone (HAZ) experiences plastic deformation followed by elastic relief at the subsequent stages. It is pointed out that the postweld deformations are on the whole characterized by a low level and remain within the permissible limits. The distribution of mechanical properties in weld joint local zones determined using the indentation method is given. The results from tensile tests and an indenter impressing test show that the weld metal has even better mechanical characteristics than the parent metal. Data are presented from metallographic investigations, which testify that there is no growth of grains in the HAZ, which is due to high rates of cooling in the used welding method. Based on the results of elaborating the electron-beam welding technology and using the developed techniques, an FWBS mockup has been fabricated that complies with the class VQC 1A tightness requirements.
机译:考虑了国际热核实验反应器(浸泡)焊接结构的刷焊结构的特定特征。提出了阐述了磨料屏蔽模块的第一壁轴承结构(FWB)中冷却系统通道盖的电子束焊接技术的结果。描述了由316L(n)钢等级钢和焊接设备制成的焊接关节样品的设计。考虑了焊接技术和对接联合设计特征,其使用使得可以获得焊缝所需的强化并避免在FWB内腔中出现金属液滴。描述了帽焊接技术过程的简化热机械模型,并提出了通过实验评估所获得的焊接结构的结构和机械状态的结果。给出了建模与实验结果之间的比较。指出,压力和应变状态在初始装载阶段以有效的方式变化。最初,在热影响区域(HAZ)中的金属体验塑性变形,然后在随后的阶段进行弹性浮雕。结果指出,邮后性变形在整个整体上,其特征在于低水平并留在允许的限制范围内。给出了使用压痕法测定的焊接接头局部区域的机械性能的分布。拉伸试验和压痕印象的结果表明,焊接金属具有比母金属更好的机械特性。数据出发了金相调查,证明了HAZ中没有谷物的生长,这是由于焊接方法中的高冷却速率。基于阐述电子束焊接技术和使用开发技术的结果,已经制造了FWBS样机,其符合VQC 1A级密封性要求。

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