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核电用异形锻件一体化成形工艺的仿真分析与研究
英文标题:Simulation analysis and research on integral forming process of profiled forgings for nuclear power
作者:张绍军 刘钊 赵东海 梁书华 
单位:苏州热工研究院有限公司 电站设备监理技术中心 
关键词:一体化封头锻件 锻造模拟软件Forge 变形温度 应力 等效应变 
分类号:TG316.2
出版年,卷(期):页码:2017,42(4):14-20
摘要:

为了研究核电用异形锻件的一体化成形工艺,利用法国Forge锻造模拟软件对一体化封头类部件热成形工序进行数值仿真模拟分析。模拟结果表明:成形后期产生径向和轴向应力极值,最大径向拉应力为118.2 MPa,产生在封头穹顶(球冠)内表面处,同时该部位应变为1.05;最大轴向拉应力为30.6 MPa,出现在封头穹顶和连接过渡区近内壁处,同时该处的应变为1.63;按Cockcroft & Latham断裂准则,这两个部位有产生裂纹的风险。在对凹模(上模)进行局部优化后,模拟结果表明上述危险部位的应力、应变分布情况明显改善。因此,凹模(上模)边缘部位的圆角是此工艺的一项重要参数,对成形后的锻件质量有一定的影响。

In order to study the integral forming process of profiled forgings for nuclear power plant, a numerical simulation of hot forming process for integral head forging was carried out by France Forge simulation software. The results show that the radial and axial stress extreme values happen at the later forming stage, and the maximum radial stress of 118.2 MPa and the strain of 1.05 appear on the inner surface of head dome (spherical). Meanwhile, the maximum axial stress of 30.6 MPa and the strain of 1.63 appear near the inner wall of the connection transition zone and the head dome. According to Cockcroft & Latham fracture criterion, the risk of cracking exists at the above positions. After the upper die being optimized locally, the simulation results show that the distributions of stress and strain at the above dangerous positions are improved. Therefore, the fillet of the upper die edge region is one of the important parameters and has a certain influence on the forging quality after forming.

基金项目:
国家科技重大专项(2011ZX06004-002)
作者简介:
张绍军(1981-),男,硕士,高级工程师 E-mail:zhangshaojun1020@163.com
参考文献:

[1]French Association for the Design, Construction and In-Service Inspection Rules for Nuclear Island Components (AFCEN). RCC-M, Design and construction rules for mechanical components of PWR nuclear islands[S]


[2]张绍军,阚玉琦.核电站核岛筒体类锻件锻造工艺参数的分析与确定[J].热加工工艺,201140(17)106-108


Zhang S J, Kan Y Q. Analysis and determination of forging process parameters of cylinder shell forgings for nuclear power plant nuclear island[J]. Hot Working Technology, 2011, 40(17): 106-108.


[3]广东核电培训中心.900 MW压水堆核电站系统与设备[M].北京:原子能出版社,2005


Guangdong Nuclear Power Training Centre. Devices & Systems of 900 MW PWR[M]. Beijing: Atomic Energy Press, 2005.


[4]朱喜斌,刘钊,阚玉琦,等. 反应堆压力容器的整体顶盖锻件质量检验的取样方法[P].中国:ZL 2012 1 0305086.X2012-08-24


Zhu X B, Liu Z, Kan Y Q, et al. Sampling method for quality inspection of integral top cover of reactor pressure vessel[P]. China: ZL 2012 1 0305086.X. 2012-08-24.


[5]华凯旋,余小鲁,王柯智.大型压力容器厚壁封头成形工艺及质量控制研究现状分析[J]. 锻压技术,2015402):8-14.


Hua K XYu X LWang K Z. Analysis of research status on forming processes and quality control of heavy pressure vessel thick-wall sealing head [J]. Forging & Stamping Technology, 2015, 40(2): 8-14.


[6]阚玉琦,黄大鹏,张绍军,等.核电站核岛大型铸锻件制造工艺评定方法研究的意义[J].热加工工艺,2010, 39(1)53-55


Kan Y Q, Huang D P, Zhang S J, et al. Study meaning of manufacturing process qualification assessment method of nuclear island large-sized casting and forging parts [J]. Hot Working Technology, 2010, 39(1): 53-55.


[7]上海发电设备成套设计研究院.压水堆核电站核岛主设备材料和焊接[M].上海:上海科学技术文献出版社,2008


Shanghai Power Equipment Research Institute. PWR Nuclear Island Main Equipment Materials and Welding [M]. Shanghai: Shanghai Scientific and Technological Literature Press, 2008.


[8]ASME2004, Boiler & pressure vessel code[S].


[9]刘璐,吴洪.反应堆压力容器整体顶盖锻件制造质量控制研究[J].热加工工艺,201140(19)120-125


Liu L, Wu H. Research on manufacturing quality control of integral top cover forging for reactor pressure vessel[J]. Hot Working Technology, 2011, 40(19): 120-125.


[10]蒲思洪,温彤,吴维,等.韧性断裂准则与阈值选取的理论及试验研究[J].热加工工艺,200938(3)18-21


Pu S H, Wen T, Wu W, et al. Theoretical and experimental research on choosing criterion and critical value of ductile fracture[J]. Hot Working Technology, 2009, 38(3): 18-21.


[11]虞松,陈军,阮雪榆.韧性断裂准则的试验与理论研究[J].中国机械工程,200617(19)2049-2052


Yu S, Chen J, Ruan X Y. Experimental and theoretical research on ductile fracture criterion[J]. China Mechanical Engineering, 2006, 17(19): 2049-2052.


 

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