Effects of Temper Embrittlement on Mechanical Properties of Hydrogenation Reactor Steel Weld Determined by Small Punch Test
摘 要
利用小冲杆试验(SPT)研究了回火脆化对加氢反应器用2.25Cr-1Mo钢焊缝在-196~22 ℃范围内力学性能的影响,获得了它的韧脆转变温度,并对SPT试样断口进行了分析。结果表明:随着试验温度的降低,2.25Cr-1Mo钢焊缝的强度明显提高;回火脆化后的屈服强度和抗拉强度较脱脆处理后的明显大,表现出一定的回火强化效应;SPT试样断裂能可以较好地表征材料的低温韧脆转变特性和回火脆化,回火脆化使得材料的韧脆转变温度升高。
Abstract
The effects of temper embrittlement on mechanical properties of the 2.25Cr-1Mo steel weld in hydrogenation reactor in the temperature range from -196 ℃ to 22 ℃ were studied by small punch test (SPT). The ductile-brittle transition temperature was obtained and the fractures of SPT specimens were analyzed. The results indicate that the tensile strength of the weld increased with temperature decreasing. The yield strength and tensile strength of specimens after temper embrittlement were significantly greater compared with the specimens after de-brittleness, which showed temper hardening effect. The fracture energy of SPT specimens can be used to characterize the low ductile-brittle transition and temper embrittlement. The ductile-brittle transition temperature of material increased because of temper embrittlement.
中图分类号 TG115.5
所属栏目 试验研究
基金项目 国家自然科学基金计划项目(51075148);国家“863”高技术研究资助项目(2012AA040105);国家科技攻关项目(2011BAK06B03)
收稿日期 2013/8/10
修改稿日期 2014/6/30
网络出版日期
作者单位点击查看
备注张恩勇(1987-),男,四川内江人,硕士研究生。
引用该论文: ZHANG En-yong,YU Can,XU Yi-fei,GUAN Kai-shu. Effects of Temper Embrittlement on Mechanical Properties of Hydrogenation Reactor Steel Weld Determined by Small Punch Test[J]. Materials for mechancial engineering, 2014, 38(11): 16~20
张恩勇,喻灿,徐一飞,关凯书. 小冲杆试验测试回火脆化对加氢反应器用钢焊缝力学性能的影响[J]. 机械工程材料, 2014, 38(11): 16~20
被引情况:
【1】徐 亮,马东方,蔡红生,耿进锋, "基于小冲杆试验技术测试P91钢的强度",机械工程材料 40, 43-48(2016)
【2】刘燕,汤杰,苏成功,王威强, "连续球压痕法测试钢管应变时效后拉伸强度的变化",理化检验-物理分册 52, 77-82(2016)
【3】黄廷尊,杨中娜,吴文烈,刘 川, "超声冲击处理对大厚度高强钢焊接接头抗拉强度的影响",机械工程材料 40, 106-110(2016)
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参考文献
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【3】杨正,杨思晟,凌祥,等.小冲孔能量法评价Q345R的屈服强度[J].塑性工程学报,2012,19(6):95-101.
【4】关凯书,黄奕昶,李璞.小冲杆测试材料屈服载荷的有限元分析[J].塑性工程学报,2007,14(6):152-156.
【5】MAO X,TAKAHASH I. Development of a further mirriaturized specimen of 3mm diameter for tem disk(3mm) smallpunch test[J].Journal of Nuclear Materials, 1987,150:42-52.
【6】钟巍华,佟振峰,张长义,等.小冲杆测试辐照对反应器压力容器钢力学性能的影响[J].金属学报,2011,47(9):1205-1209.
【7】FINARELLI D, CARSUGHI F,JUNG P. The small ball punch test at FZJ[J].Journal of Nuclear Materials,2008,337:65-71.
【8】刘加高,饶谋生,左上军. 材料韧脆转变温度数据处理方法[J].化学工程与装备,2010(4):90-91.
【9】周玉昌,夏翔鸣. CrMo钢材料韧脆转变温度曲线的回归分析[J].压力容器, 2003,20(6):13-18.
【10】KIM M C,OH Y J,LEE B S.Evaluation of ductile-brittle transition temperature before and after neutron irradiation for RPV steels using small punch tests[J].Nuclear Engineering and Design,2005,235:1799-1805.
【11】SHEKHTER A, KIM S, CARR D G, et al. Assessment of mechanical properties of the martensitic steel EUROFER97 by means of punch tests[J].International Journal of Pressure Vessels and Piping, 2002,79:611-615.
【12】BULLOCH J H. Toughness losses in low alloy steels at high temperatures:an appraisal of certain factors concerning the small punch test[J].International Journal Pressure Vessels and Piping,1998,75:791-804.欢迎来稿欢迎订阅欢迎刊登广告
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