Understanding the Mechanistic Role of Lithium in Accelerated Corrosion of Zirconium Alloys Using Advanced Characterization and Atomistic Simulation-Reference-Cited by-同舟云学术

Understanding the Mechanistic Role of Lithium in Accelerated Corrosion of Zirconium Alloys Using Advanced Characterization and Atomistic Simulation

Published:2023-11-01 Issue: Volume: Page:356-386
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Container-title:Zirconium in the Nuclear Industry: 20th International Symposium
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Author:

Garner Alistair¹²,Gillen Conor¹^ORCID,Stephens Gareth³^ORCID,Styman Paul⁴,Armson Sam¹^ORCID,Robinson Jacqueline¹,Liu Junliang⁵^ORCID,Carruthers Alexander²,Pickering Felicity¹^ORCID,Sherry Sarah¹,Chan ChoenMay¹,Fenwick Mark¹,Hulme Helen¹,Ortner Susan⁴,Riley Chris⁶,Grovenor Chris⁵,Frankel Philipp²,Middleburgh Simon C.³^ORCID,Cole-Baker Aidan¹

Affiliation:

1. Jacobs, Walton House, Birchwood Park, Warrington, WA3 6GA, GB

2. Dept. of Materials, University of Manchester, Oxford Rd., M13 9PL, GB

3. Nuclear Futures Institute, Bangor University, Bangor, LL57 1UT, GB

4. National Nuclear Laboratory, Culham Science Centre, Abingdon, OX14 3DB, GB

5. Dept. of Materials, University of Oxford, Parks Rd., OX1 3PH, GB

6. Rolls-Royce, Raynesway, Derby, DE21 7BE, GB

Publisher

ASTM International

Reference49 articles.

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3. F. Garzarolli, J. Pohlmeyer, S. Trapp-Pritsching, and H. G. Weidinger, “Influence of Various Additions to Water on Zircaloy-4 Corrosion in Autoclave Tests at 350°C,” in Proceedings of the IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion of Zr-Alloys in Water Reactor Environments (Vienna, Austria: International Atomic Energy Agency, 1990), 65–72.

4. I. L. Bramwell, P. D. Parsons, and D. Tice, “Corrosion of Zircaloy-4 PWR Fuel Cladding in Lithiated and Borated Water Environments,” in Zirconium in the Nuclear Industry: 9th International Symposium, ed. C. M. Eucken and A. M. Garde (West Conshohocken, PA: ASTM International, 1991), 628–642, https://doi.org/10.1520/STP25532S

5. D. Pêcheur, J. Godlewski, J. Peybernès, L. Fayette, M. Noé, A. Frichet, and O. Kerrec, “Contribution to the Understanding of the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding,” in Zirconium in the Nuclear Industry: 12th International Symposium, ed. G. P. Sabol and G. D. Moan (West Conshohocken, PA: ASTM International, 2000), 793–811, https://doi.org/10.1520/STP14328S