Home
Editorial Committee
Brief Instruction
Back Issues
Instruction to Authors
Submission on line
Contact Us
Chinese

  The journal resolutely  resists all academic misconduct, once found, the paper will be withdrawn immediately.

Title:Simulation analysis and research on integral forming process of profiled forgings for nuclear power
Authors: Zhang Shaojun  Liu Zhao  Zhao Donghai  Liang Shuhua 
Unit: Equipment Supervision Research Center  Suzhou Nuclear Power Research Institute Co.  Ltd. 
KeyWords: integral head forging  Forge forging simulation software  deformation temperature  stress  equivalent strain 
ClassificationCode:TG316.2
year,vol(issue):pagenumber:2017,42(4):14-20
Abstract:

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.

Funds:
国家科技重大专项(2011ZX06004-002)
AuthorIntro:
张绍军(1981-),男,硕士,高级工程师 E-mail:zhangshaojun1020@163.com
Reference:

[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.


 

Service:
This site has not yet opened Download Service】【Add Favorite
Copyright Forging & Stamping Technology.All rights reserved
 Sponsored by: Beijing Research Institute of Mechanical and Electrical Technology; Society for Technology of Plasticity, CMES
Tel: +86-010-62920652 +86-010-82415085     Fax:+86-010-62920652
Address: No.18 Xueqing Road, Beijing 100083, P. R. China
 E-mail: fst@263.net    dyjsgg@163.com