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锆合金板材微孔成形数值模拟与实验研究

Numerical simulation and experimental study on microporous forming of zirconium alloy sheet
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摘要 锆合金由于其优良的抗腐蚀能力和低的热中子吸收截面被广泛应用于核能领域,但是目前针对锆合金的塑性加工性能研究较少,这限制了锆合金的使用场合和使用范围。本文基于数值模拟和实验研究了锆合金板材上微孔的压印成型过程,分析了锆合金板材上微孔的成型特点及材料塑性流动变化情况,探讨了锆合金板材上微孔成型规律。结果表明利用压印成型技术可有效的在锆合金板材上加工制备出满足要求的微孔,这对锆合金板材的进一步利用具有重要的意义。 Zirconium alloys are widely used in the field of nuclear energy due to its excellent corrosion resistance and low thermal neutron absorption cross-section.However,there are few studies on the plastic processing properties of zirconium alloys,which limits the application occasions and scope of zirconium alloys.Based on the numerical simulation and experiment,the coining process of microporous on zirconium alloy sheet was studied in this paper.The forming characteristics of microporous on zirconium alloy sheet and the change of material plastic flow are analyzed,and the forming law of microporous on zirconium alloy sheet was discussed.The results show that the coining technology can effectively process the microporous that meet the requirements on the zirconium alloy sheet,which is of great significance to the further utilization of the zirconium alloy sheet.
作者 付明 刘剑锋 向涛 柏强 罗远新 FU Ming;LIU Jian-feng;XIANG Tao;BAI Qiang;LUO Yuan-xin(Nuclear Power Institute of China,Chengdu 610200,China;State Key Laboratory of mechanical transmission,Chongqing University,Chongqing 400044,China)
出处 《重型机械》 2021年第3期45-49,共5页 Heavy Machinery
关键词 微孔 压印 数值模拟 microporous coining numerical simulation
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  • 1李中奎,刘建章,周廉,李聪,赵文金,张建军.新锆合金耐蚀性能研究[J].原子能科学技术,2003,37(z1):84-87. 被引量:11
  • 2王辉,胡石林,杨启法,张平柱,袁改焕,薛祥义.国产新型锆铌合金水侧腐蚀行为研究[J].原子能科学技术,2007,41(z1):342-347. 被引量:1
  • 3李佩志.我国锆合金的研究现状[J].稀有金属材料与工程,1993,22(4):7-16. 被引量:14
  • 4赵文金,周邦新,苗志,彭倩,蒋有荣,蒋宏曼,庞华.我国高性能锆合金的发展[J].原子能科学技术,2005,39(B07):2-9. 被引量:94
  • 5黄强.锆合金耐腐蚀性能研究综述[J].核动力工程,1996,17(3):262-267. 被引量:16
  • 6Yang Wendou(杨文斗).Reactor Materials Science(反应堆材料学)[M].Beijing:Atomic Energy Press,2006:260.
  • 7LiPeizhi(李佩志).核反应堆用新锆合金研究现状[J].稀有金属材料与工程.1999,29(03):185一186.
  • 8Marolon J P, Garner G, Beslu P, et ul. Update on the Develop- ment of Advanced Zirconium Alloys fnr RWB Fuel Rod Claddings [ C ]// Proceedings of ANS Fuel Perfirmunce ConJbrence in Port- land (USA). USA: ANS, 1997:331 -336.
  • 9Nikulina A V, Markelov V A, Peregud M M, el al. Zircunium Alloy E635 as a Material for Fuel Fod Cladding and Other Com- ponents of VVER and RBMK Cores [ C ]// Bradley E R, Sabol G P. Zirconium in the Nuclear lndusto'. Philadelphia: America Society for Testing and Materials, 1996:785 -804.
  • 10Jeong Y H, Park S Y, Lee M H, et al. Out-of-Pile and In-Pile Perfornmnce of Advanced Zirconium Alloys (HANA) for High Burn-Up Fuel [ J]. Journal of Nuclear Science and Technolugy, 2006, 43(9) : 977 -983.

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