Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors
- 1 July 1975
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 57 (1), 11-33
- https://doi.org/10.1016/0022-3115(75)90175-0
Abstract
No abstract availableKeywords
This publication has 5 references indexed in Scilit:
- Investigation of Stress Corrosion Cracking Susceptibility of Fe-Ni-Cr Alloys in Nuclear Reactor Water EnvironmentsCorrosion, 1973
- A new model for hydrogen-assisted cracking (hydrogen “embrittlement”)Metallurgical Transactions, 1972
- Intercrystalline stress corrosion cracking of inconel 600 inspection tubes in the Ågesta reactorNuclear Engineering and Design, 1967
- Stainless-Steel-Clad Fuel Rod FailuresNuclear Applications, 1965
- Corrosion Aspects of Iron, Austenitic Stainless Steel and Inconel in High Temperature WaterCorrosion, 1964