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Irradiation-assisted stress corrosion cracking susceptibility and mechanical properties related to irradiation-induced microstructures of 304L austenitic stainless steel
Irradiation-assisted stress corrosion cracking susceptibility and mechanical properties related to irradiation-induced microstructures of 304L austenitic stainless steel
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Irradiation-assisted stress corrosion cracking susceptibility and mechanical properties related to irradiation-induced microstructures of 304L austenitic stainless steel

Paccou, Elie ; Tanguy, Benoît ; Legros, Marc

Journal of nuclear materials, 2020-01, Vol.528, p.151880, Article 151880 [Periódico revisado por pares]

Amsterdam: Elsevier B.V

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Temperature increase of Zircaloy-4 cladding tubes due to plastic heat dissipation during tensile tests at 0.1–10 s−1 strain rates
Temperature increase of Zircaloy-4 cladding tubes due to plastic heat dissipation during tensile tests at 0.1–10 s−1 strain rates
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Temperature increase of Zircaloy-4 cladding tubes due to plastic heat dissipation during tensile tests at 0.1–10 s−1 strain rates

Hellouin de Menibus, Arthur ; Auzoux, Quentin ; Besson, Jacques ; Crépin, Jérôme

Journal of nuclear materials, 2014-11, Vol.454 (1-3), p.247-254 [Periódico revisado por pares]

Elsevier

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Influence of the U3O7 domain structure on cracking during the oxidation of UO2
Influence of the U3O7 domain structure on cracking during the oxidation of UO2
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Influence of the U3O7 domain structure on cracking during the oxidation of UO2

DESGRANGES, L ; PALANCHER, H ; GAMALERI, M ; MICHA, J. S ; OPTASANU, V ; RACEANU, L ; MONTESIN, T ; CRETON, N

Journal of nuclear materials, 2010-07, Vol.402 (2-3), p.167-172 [Periódico revisado por pares]

Amsterdam: Elsevier

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