Derek H. Lister
Affiliations: | University of New Brunswick (Canada) |
Area:
Civil EngineeringGoogle:
"Derek Lister"Children
Sign in to add traineeMahsa Khatibi | grad student | 2010 | University of New Brunswick (Canada) |
Kittima Khumsa-Ang | grad student | 2011 | University of New Brunswick (Canada) |
BETA: Related publications
See more...
Publications
You can help our author matching system! If you notice any publications incorrectly attributed to this author, please sign in and mark matches as correct or incorrect. |
Weerakul S, Leaukosol N, Lister DH, et al. (2020) Effects on Flow-Accelerated Corrosion of Oleylpropanediamine Under Single-Phase Water Conditions Pertinent to Power Plant Feedwater Corrosion. 76: 217-230 |
Huang J, Lister D, Uchida S. (2020) The corrosion of aluminum alloy and release of hydrogen in nuclear reactor emergency core coolant: Implications for deflagration and explosion risk Nuclear Engineering and Design. 359: 110458 |
Huang J, Lister D, Uchida S, et al. (2019) The corrosion of aluminium alloy and release of intermetallic particles in nuclear reactor emergency core coolant: Implications for clogging of sump strainers Nuclear Engineering and Technology. 51: 1345-1354 |
Uchida S, Hanawa S, Naitoh M, et al. (2017) An empirical model for the corrosion of stainless steel in BWR primary coolant Corrosion Engineering Science and Technology. 52: 587-595 |
Lister D, Uchida S. (2015) Determining water chemistry conditions in nuclear reactor coolants Journal of Nuclear Science and Technology. 52: 451-466 |
Suzuki H, Uchida S, Naitoh M, et al. (2013) Risk Evaluation of Flow-Accelerated Corrosion Based on One-Dimensional FAC Code Nuclear Technology. 183: 194-209 |
Uchida S, Naitoh M, Okada H, et al. (2012) Determination Procedures of High Risk Zones for Local Wall Thinning Due to Flow-Accelerated Corrosion Nuclear Technology. 180: 65-77 |
Uchida S, Naitoh M, Okada H, et al. (2012) Verification and Validation of Evaluation Procedures for Local Wall Thinning Due to Flow-Accelerated Corrosion and Liquid Droplet Impingement Nuclear Technology. 178: 280-297 |
Ishida K, Lister D. (2012) In situ measurement of corrosion of type 316L stainless steel in 553 K pure water via the electrical resistance of a thin wire Journal of Nuclear Science and Technology. 49: 1078-1091 |
Uchida S, Naitoh M, Uehara Y, et al. (2009) Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (III): Evaluation of Wall Thinning Rate with the Coupled Model of Static Electrochemical Analysis and Dynamic Double Oxide Layer Analysis Journal of Nuclear Science and Technology. 46: 31-40 |