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等离子焊连续油管焊接热影响区组织及性能热模拟分析 被引量:6

Thermal Simulation on Microstructure and Properties of Heat-affected Zone in Coiled Tubing by Plasma Welding
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摘要 采用热模拟技术、显微分析方法和力学性能测试等手段,对连续油管用粒状贝氏体钢等离子熔化焊焊接接头热影响区不同部位的微观组织和宏观力学性能进行了分析,并与母材组织及力学性能进行了对比。结果表明,在接头热影响区中,过热粗晶区以长条状铁素体组织为主,断口形貌以均匀的韧窝为主,韧窝大且深,韧性较好,冲击功相对较高;正火区和不完全正火区组织以多边形铁素体为主,晶粒之间晶界清晰,断口以准解理断裂为主,冲击功较低;回火区没有发生明显相变,晶粒尺寸比母材略有增加,组织发生了微小的回复再结晶,材料的冲击功有所回复。 The microstructure and properties of heat-affected zone(HAZ) in granular bainite coiled tubing were analyzed by thermal simulation technique,microscopic analysis method and mechanical property testing,and the properties of HAZ was compared with the base material.The results show that overheated coarse grain zone is composed of strip ferrite-based,fracture surface is composed of uniform dimple-based,which are broad and deep.The fracture toughness is good and the impact energy is relatively high.The microstructure of normalizing area and not fully normalizing area are mainly composed of polygonal ferrite,clear grain boundary between grains.The fracture surface is mainly quasi-cleavage fracture,impact energy is relatively low.There is not obvious phase change in temper zone.The grain size of temper zone increases slightly compared with the base material,a small recovery and recrystallization appear in the zone.The impact energy of material rises slightly.
出处 《热加工工艺》 CSCD 北大核心 2011年第3期136-139,共4页 Hot Working Technology
基金 陕西省教育厅自然科学基金资助项目(00k904) 陕西省重点学科建设专项资金资助项目(00X901)
关键词 连续油管 粒状贝氏体钢 热模拟技术 等离子熔化焊 coiled tubing granular bainitic steel thermal simulation technique plasma welding
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  • 1Fermer D, Toffoli T, Wolfram S. Cellular automata, proceedings of an interdisciplinary workshop [J]. Phsica D: Nonlinear Phenomena, 1984, 10D (1-2): 247-255.
  • 2Sawai T, Shiba K, Hishinuma A. Microstructure of welded and thermal-aged low activation steel F82H IEA heat [J]. Journal of Nuclear Materials, 2000, 283-287(1): 657-661.
  • 3Xuejun Jia, Dai Y. Microstructure and mechanical properties of F82H weld metal irradiated in SINQ target-3 [J]. Journal of Nuclear Materials, 2004, 329-333(1): 309-313.

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