Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments
Accident tolerant fuel (ATF) are currently being developed as part of an international effort to modify or replace zirconium-based cladding materials in light water reactors. The main objective of ATF cladding materials is to improve fuel reliability and safety during accident scenarios. Thus, these...
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Elsevier
2023-12-01
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Series: | Nuclear Materials and Energy |
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Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179123001588 |
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author | Rajnikant V. Umretiya Michael Worku Hamdy Abouelella Wanming Zhang Raul B. Rebak Andrew K. Hoffman Jessika V. Rojas |
author_facet | Rajnikant V. Umretiya Michael Worku Hamdy Abouelella Wanming Zhang Raul B. Rebak Andrew K. Hoffman Jessika V. Rojas |
author_sort | Rajnikant V. Umretiya |
collection | DOAJ |
description | Accident tolerant fuel (ATF) are currently being developed as part of an international effort to modify or replace zirconium-based cladding materials in light water reactors. The main objective of ATF cladding materials is to improve fuel reliability and safety during accident scenarios. Thus, these materials should perform comparable to or better than the current zirconium alloy. One of the ATF concepts explores modifying standard Zircaloy cladding by coating their outer surface. In this study, surface-modified Zr-4 is produced by depositing a protective coating of chromium through two different coating techniques, Physical Vapor Deposition (PVD) and Cold Spray (CS). The coated specimens were tested at ∼300 °C in out-of-pile autoclaves simulating Boiling Water Reactor (BWR) conditions. Results show that after one month of immersion, Cr-coated Zr-4 evidenced a small mass gain in hydrogenated environments. However, both types of coated specimens showed significant coating degradation and mass loss in oxygenated environments. |
first_indexed | 2024-03-09T02:15:21Z |
format | Article |
id | doaj.art-e58d16e12e664e63bdc9211bddaa0f1d |
institution | Directory Open Access Journal |
issn | 2352-1791 |
language | English |
last_indexed | 2024-03-09T02:15:21Z |
publishDate | 2023-12-01 |
publisher | Elsevier |
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series | Nuclear Materials and Energy |
spelling | doaj.art-e58d16e12e664e63bdc9211bddaa0f1d2023-12-07T05:28:52ZengElsevierNuclear Materials and Energy2352-17912023-12-0137101519Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environmentsRajnikant V. Umretiya0Michael Worku1Hamdy Abouelella2Wanming Zhang3Raul B. Rebak4Andrew K. Hoffman5Jessika V. Rojas6GE Research, Schenectady, NY 12309, USA; Corresponding authors.GE Research, Schenectady, NY 12309, USAGE Research, Schenectady, NY 12309, USAGE Research, Schenectady, NY 12309, USAGE Research, Schenectady, NY 12309, USAGE Research, Schenectady, NY 12309, USAVirginia Commonwealth University, Richmond, VA 23284, USA; Corresponding authors.Accident tolerant fuel (ATF) are currently being developed as part of an international effort to modify or replace zirconium-based cladding materials in light water reactors. The main objective of ATF cladding materials is to improve fuel reliability and safety during accident scenarios. Thus, these materials should perform comparable to or better than the current zirconium alloy. One of the ATF concepts explores modifying standard Zircaloy cladding by coating their outer surface. In this study, surface-modified Zr-4 is produced by depositing a protective coating of chromium through two different coating techniques, Physical Vapor Deposition (PVD) and Cold Spray (CS). The coated specimens were tested at ∼300 °C in out-of-pile autoclaves simulating Boiling Water Reactor (BWR) conditions. Results show that after one month of immersion, Cr-coated Zr-4 evidenced a small mass gain in hydrogenated environments. However, both types of coated specimens showed significant coating degradation and mass loss in oxygenated environments.http://www.sciencedirect.com/science/article/pii/S2352179123001588Accident tolerant fuelCr-coated Zr-4CorrosionSEM/EDSXRD |
spellingShingle | Rajnikant V. Umretiya Michael Worku Hamdy Abouelella Wanming Zhang Raul B. Rebak Andrew K. Hoffman Jessika V. Rojas Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments Nuclear Materials and Energy Accident tolerant fuel Cr-coated Zr-4 Corrosion SEM/EDS XRD |
title | Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments |
title_full | Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments |
title_fullStr | Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments |
title_full_unstemmed | Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments |
title_short | Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments |
title_sort | hydrothermal corrosion of pvd and cold spray cr coatings on zircaloy 4 in hydrogenated and oxygenated lwr coolant environments |
topic | Accident tolerant fuel Cr-coated Zr-4 Corrosion SEM/EDS XRD |
url | http://www.sciencedirect.com/science/article/pii/S2352179123001588 |
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