Evaluation of irradiation assisted stress corrosion cracking (IASCC) of type 316 stainless steel irradiated in FBR
- 1 December 1993
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 207, 159-168
- https://doi.org/10.1016/0022-3115(93)90258-z
Abstract
No abstract availableKeywords
This publication has 6 references indexed in Scilit:
- Radiation-induced grain boundary segregation and sensitization of a neutron-irradiated austenitic stainless steelPublished by Elsevier ,2003
- Fundamental Research for Evaluation of IASCC SusceptibilityZairyo-to-Kankyo, 1993
- Radiation-induced sensitization of a titanium-modified austenitic stainless steel irradiated in a spectral-tailored experiment at 60–400°CJournal of Nuclear Materials, 1992
- Microstructural evolution of austenitic stainless steels irradiated in spectrally tailored experiment in ORR at 400°CJournal of Nuclear Materials, 1992
- Evaluation of Radiation-Induced Sensitization of Austenitic Stainless Steels Using Electrochemical Potentiokinetic Reactivation TechniqueCorrosion, 1990
- Swelling behavior of austenitic stainless steels in a spectrally tailored reactor experiment: Implications for near-term fusion machinesJournal of Nuclear Materials, 1988