Microstructure, mechanical properties and IASCC susceptibility of stainless steel baffle bolts after 30 years of operation in a PWR
Authors:
- Rik-Wouter BoschRBRik-Wouter Bosch
- Wouter Van RenterghemWRWouter Van Renterghem
- Steven Van DyckSDSteven Van Dyck
- Rachid ChaouadiRCRachid Chaouadi
- Robert GérardRGRobert Gérard
- Frédéric SomvilleFSFrédéric Somville
- 1 January 2021
- journal article
- research article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 543
Abstract
No abstract availableKeywords
This publication has 18 references indexed in Scilit:
- A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steelsJournal of Nuclear Materials, 2011
- Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core EnvironmentsCorrosion, 2007
- IASCC Susceptibility and Slow Tensile Properties of Highly-irradiated 316 Stainless SteelsJournal of Nuclear Science and Technology, 2004
- Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructureJournal of Nuclear Materials, 2004
- Fracture toughness and crack growth rates of irradiated austenitic stainless steels.2003
- 2000 F.N. Speller Award Lecture: Stress Corrosion Cracking in Pressurized Water Reactors—Interpretation, Modeling, and RemediesCorrosion, 2000
- Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internalsJournal of Nuclear Materials, 1999
- A review of irradiation assisted stress corrosion crackingJournal of Nuclear Materials, 1994
- Effects of Neutron Irradiations at Temperatures Below 500°C on the Properties of Cold Worked 316 Stainless Steels: A Review1994
- The evolution of mechanical property change in irradiated austenitic stainless steelsJournal of Nuclear Materials, 1993