Stress Corrosion Cracking Susceptibility of Low Alloy Steels Used for Reactor Pressure Vessel in High Temperature Oxygenated Water
Author:
Affiliation:
1. Hitachi Research Laboratory, Hitachi, Ltd., Hitachi-shi, Ibaraki-ken, Japan
2. Hitachi Works, Hitachi, Ltd., Hitachi-shi, Ibaraki-ken, Japan
3. Kure Works, Babcock-Hitachi, Ltd., Kure-shi, Hiroshima-ken, Japan
Abstract
Publisher
ASME International
Subject
Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality
Link
http://asmedigitalcollection.asme.org/pressurevesseltech/article-pdf/107/4/430/5850576/430_1.pdf
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1. Environmentally-assisted cracking of carbon and low-alloy steels in light water reactors;Nuclear Corrosion;2020
2. Localized corrosion of pressure vessel steel in a boiling water reactor cladding flaw – modeling of electrochemical conditions and dedicated experiments;Electrochimica Acta;2017-07
3. Effect of chloride and sulfate additions on corrosion of low alloy steel in high-temperature water;Electrochimica Acta;2015-08
4. Effect of Chloride on the Oxides on Low-Alloyed Steel in Conditions of a Light Water Reactor Pressure Vessel Cladding Flaw;Journal of The Electrochemical Society;2014
5. Stress Corrosion Cracking of Low Alloy Steels under BWR Conditions; Assessment of Crack Growth Rate Algorithms;Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors;2013-10-04
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