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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water... 2019 2026 2021 2023 268
  1. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors (2019)
    Jean-Christophe Brachet, Marion Le Flem et al. Journal of Nuclear Materials

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Citing Papers

Autoclave grid-to-rod fretting corrosion behaviors of the Zr alloy fuel cladding with and without Cr coating through advanced characterization
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Works of C. Phalippou being referenced

Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors
2019 Standout

Author Peers

Author Last Decade Papers Cites
C. Phalippou 132 331 14 192 11 401
Ross A. Antoniou 234 142 5 97 13 425
P. E. Magnusen 199 161 3 143 9 366
Pengjiao Chong 76 127 6 130 10 338
Ningyu Du 123 254 2 34 15 369
M. Elmadagli 141 218 2 172 13 434
Guofeng Han 132 143 10 75 19 372
Sylwester Błacha 52 132 4 38 11 401
John Knott 123 148 5 117 16 343
David Lanning 280 92 7 46 17 351
Alfonso Campos‐Amezcua 143 58 54 128 13 344

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