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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

Journal of Nuclear Materials · 2019 · Vol. 517 · pp. 268–285
Jean-Christophe BrachetIsabel Idarraga-TrujilloMarion Le FlemMatthieu Le SauxValérie VandenbergheStéphane UrvoyElodie RouesneThomas GuilbertCaroline Toffolon-MascletMarc TupinC. PhalippouFernando LomelloFrédéric SchusterAlain BillardGihan VelişaC. DucrosFrédéric Sanchette
Nuclear Materials and PropertiesFusion materials and technologiesNuclear reactor physics and engineeringMaterials scienceZirconium alloyCladding (metalworking)EmbrittlementCeramicFrettingMetallurgyLight-water reactorNuclear fuelNitride
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References
Stress-related effects in thin films
Thin Solid Films · 1989 · 1,137 citations
Accident tolerant fuels for LWRs: A perspective
Journal of Nuclear Materials · 2013 · 1,030 citations
Accident tolerant fuel cladding development: Promise, status, and challenges
Journal of Nuclear Materials · 2018 · 899 citations
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