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	Modeling flow stress constitutive behavior of SA508-3 steel for nuclear reactor pressure vessels
	M. Y. Sun ; L. H. Hao ; S. J. Li ; D. Z. Li ; Y. Y. Li
刊名	Journal of Nuclear Materials
	2011
卷号	418期号:1-3页码:269-280
关键词	low-alloy steels low-carbon steel hot deformation mechanical-properties fracture-toughness temperature austenite working
ISSN号	0022-3115
中文摘要	Based on the measured stress-strain curves under different temperatures and strain rates, a series of flow stress constitutive equations for SA508-3 steel were firstly established through the classical theories on work hardening and softening. The comparison between the experimental and modeling results has confirmed that the established constitutive equations can correctly describe the mechanical responses and microstructural evolutions of the steel under various hot deformation conditions. We further represented a successful industrial application of this model to simulate a forging process for a large conical shell used in a nuclear steam generator, which evidences its practical and promising perspective of our model with an aim of widely promoting the hot plasticity processing for heavy nuclear components of fission reactors. (c) 2011 Elsevier B.V. All rights reserved.
原文出处	://WOS:000297233500034
公开日期	2012-04-13
内容类型	期刊论文
源URL	[http://210.72.142.130/handle/321006/30686]
专题	金属研究所_中国科学院金属研究所
推荐引用方式 GB/T 7714	M. Y. Sun,L. H. Hao,S. J. Li,et al. Modeling flow stress constitutive behavior of SA508-3 steel for nuclear reactor pressure vessels[J]. Journal of Nuclear Materials,2011,418(1-3):269-280.
APA	M. Y. Sun,L. H. Hao,S. J. Li,D. Z. Li,&Y. Y. Li.(2011).Modeling flow stress constitutive behavior of SA508-3 steel for nuclear reactor pressure vessels.Journal of Nuclear Materials,418(1-3),269-280.
MLA	M. Y. Sun,et al."Modeling flow stress constitutive behavior of SA508-3 steel for nuclear reactor pressure vessels".Journal of Nuclear Materials 418.1-3(2011):269-280.

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