锻压技术

核电Inconel690管材挤压模拟与实验研究

英文标题：Simulation and experiment of nuclear power Inconel 690 pipe extrusion

作者：齐麦顺

单位：燕山大学继续教育学院

关键词：热加工图固溶拉伸金相组织

分类号：TG113；TG376.2

出版年,卷(期):页码：2010,35(4):116-123

摘要：

根据Inconel 690合金热加工图，用数值模拟方法确定了Inconel 690合金管材挤压的加热温度T=1200 ℃和应变速率及与之相应的挤压速度V=80 mm·s^-1。依据核电装备对Inconel 690合金管材组织和力学性能方面的技术要求，通过对棒材进行挤压和固溶处理以及拉伸实验，确定了适合的挤压比为6和10。考虑到液压机最大压力为3000 kN，选取挤压比8，经数值模拟得出最大挤压力为2360 kN，符合液压机最大压力条件。

Based on the hot working graph of Inconel 690 alloy, the heating temperature（1200 ℃）, strain rate and the corresponding extrusion rate（80 mm·s^-1）were determined by using numerical simulation method. The suited extrusion ratio(6 and 10) was gained by the microstructure and mechanical performance technical requirements of nuclear power equipment. The extrusion ratio of 8 was selected in view of the maximum hydraulic pressure (3000 kN), and the obtained maximum hydraulic pressure by numerical simulation (2360 kN) was consitent with the condition of max-pressure of hydropress.

基金项目：

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