A Representative Volume Element Model for Investigating the Hydride Inclusion Effect on Ductility of Zry-Based Nuclear Fuel Cladding
Author:
Publisher
Springer Science and Business Media LLC
Subject
Multidisciplinary
Link
https://link.springer.com/content/pdf/10.1007/s13369-023-08264-z.pdf
Reference43 articles.
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2. Kammenzind, B.: American Society for Testing and Materials eds: Zirconium in the nuclear industry: 15th international symposium, Sunriver, Oregon, USA, June 24 - 28, 2007. ASTM International, West Conshohocken, PA (2009)
3. Motta, A.T.; Capolungo, L.; Chen, L.-Q.; Cinbiz, M.N.; Daymond, M.R.; Koss, D.A.; Lacroix, E.; Pastore, G.; Simon, P.-C.A.; Tonks, M.R.; Wirth, B.D.; Zikry, M.A.: Hydrogen in zirconium alloys: a review. J. Nucl. Mater. 518, 440–460 (2019). https://doi.org/10.1016/j.jnucmat.2019.02.042
4. Sindelar, R., Louthan, M., Pnnl, B.: White Paper Summary of 2nd ASTM International Workshop on Hydrides in Zirconium Alloy Cladding. (2015)
5. Konarski, P.; Cozzo, C.; Khvostov, G.; Ferroukhi, H.: Spent nuclear fuel in dry storage conditions–current trends in fuel performance modeling. J. Nucl. Mater. 555, 153138 (2021). https://doi.org/10.1016/j.jnucmat.2021.153138
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