核电关键结构材料在高温水环境中的应力腐蚀破裂及其定量预测_图(精)[大全五篇]

第一篇：核电关键结构材料在高温水环境中的应力腐蚀破裂及其定量预测_图(精)

相关换算关系。针对无法用破坏性方法测量实际构件局部强度的核电工程状况，可利用本工作结果用硬度 测量来估计其屈服强度，然后利用有关公式和数据来定量预测应力腐蚀裂纹扩展速率和构件寿命。参考文献 [1] Karen Gott, Cracking data base as a basis for risk informed inspection, Proceedings of Tenth International Conference on Environmental Degradation on Materials in Nuclear Power Systems – Water Reactors, August, 2001，USA(NACE, 2002 [2] 丁训慎，腐蚀与防护，2002 年第 10 期，pp.441-444 [3] R.W.Staehle，J.A.Gorman，Corrosion，2003，vol.59, pp.931-994 [4] Barry C.Syrett, Jeffery A.Gorman, Materials Performance, 2003, vol.42, No.2 pp 32-38 [5] F.P.Ford, Corrosion，1996，vol.52, pp.375-.[6] T.Shoji, S.Suzuki, R.G.Ballinger, Theoretical prediction of SCC growth behavior-threshold and plateau growth rate, Proc.7th Int.Symp.on Environmental Degradation in Nuclear Power Systems-Water Reactors, Breckenridge, Colorado, USA, August 7-10, 1995, NACE, Houston, p.881.[7] Y.C.Gao and K.C.Hwang, in: Advances in fracture research, Proc.5th Int.Conf.on Fracture, Cannes, France, 29 March-3 April 1981, Pergamon, Oxford and New York, 1982,vol.2, p.669.[8] W.W.Gerberich, D.L.Davidson, M.Kaczorowski, J.Mech.Phys.Solids 38(1990 87.[9] Peter L.Andresen and Martin M.Morra，Scc of stainless steels and ni alloys in high temperature water, CORROSION/2007, NACE International, Houston, TX, 2007, Paper No.07612 [10] 陈冰川, 李光福, 杨武, 奥氏体不锈钢里氏硬度与维氏硬度及强度之间的换算关系,机械工程材料，已 接受待发表于 2009-6-6