A study of life prediction differences for a nickel-base Alloy 690 using a threshold and a non-threshold model
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference21 articles.
1. V.N. Shah, P.E. McDonald, Aging and Life Extension of Major Light Water Reactor Components, Elsevier Publishers, Amsterdam, The Netherlands, 1993.
2. A Stress Corrosion Cracking Evaluation of Inconel 690 for Steam Generator Tubing Applications
3. Stress Corrosion Cracking of Alloys 600 and 690 and Nos. 82 and 182 Weld Metals in High Temperature Water
4. Relative stress corrosion susceptibilities of alloys 690 and 600 in simulated boiling water reactor environments
5. Stress Corrosion Cracking of Inconel Alloys and Weldments in High-Temperature Water — the Effect of Sulfuric Acid Addition
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1. Crack growth rate evaluation of alloys 690/152 by numerical simulation of extracted CT specimens;Nuclear Engineering and Technology;2019-10
2. Corrosion Fatigue Crack Growth Behavior of Alloy 690 in High-Temperature Pressurized Water;CORROSION;2017-01-19
3. Technical Note:Frequency Dependence of Fatigue Crack Growth Rate of Alloy 690TT in High-Temperature Boron-Lithium Water;CORROSION;2015-10
4. Reactive Molecular Dynamics of the Initial Oxidation Stages of Ni(111) in Pure Water: Effect of an Applied Electric Field;The Journal of Physical Chemistry A;2012-11-26
5. Ab initio study of influence of 3d alloying elements on corrosion properties of non-passivated nickel-base alloys;Journal of Nuclear Materials;2011-11
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