Filtros : "Abe, Alfredo" Limpar

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  • Source: Nuclear Engineering and Technology. Unidade: EP

    Subjects: AÇO INOXIDÁVEL, REVESTIMENTOS, ALTA TEMPERATURA, LIGAS METÁLICAS

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    • ABNT

      AVELAR, Alan Matias et al. Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance. Nuclear Engineering and Technology, v. 55, p. 156-168, 2023Tradução . . Disponível em: https://doi.org/10.1016/j.net.2022.09.002. Acesso em: 28 abr. 2024.
    • APA

      Avelar, A. M., Camargo, F. de, Silva, V. S. P. da, Giovedi, C., Abe, A., & Mourão, M. B. (2023). Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance. Nuclear Engineering and Technology, 55, 156-168. doi:10.1016/j.net.2022.09.002
    • NLM

      Avelar AM, Camargo F de, Silva VSP da, Giovedi C, Abe A, Mourão MB. Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance [Internet]. Nuclear Engineering and Technology. 2023 ;55 156-168.[citado 2024 abr. 28 ] Available from: https://doi.org/10.1016/j.net.2022.09.002
    • Vancouver

      Avelar AM, Camargo F de, Silva VSP da, Giovedi C, Abe A, Mourão MB. Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance [Internet]. Nuclear Engineering and Technology. 2023 ;55 156-168.[citado 2024 abr. 28 ] Available from: https://doi.org/10.1016/j.net.2022.09.002
  • Source: Nuclear Engineering and Design. Unidade: EP

    Subjects: USINAS NUCLEARES, AÇO INOXIDÁVEL

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    • ABNT

      AVELAR, Alan Matias et al. Best estimate plus uncertainty analysis of metal-water reaction transient experiment. Nuclear Engineering and Design, v. 411, p. 12 , 2023Tradução . . Disponível em: https://doi.org/10.1016/j.nucengdes.2023.112414. Acesso em: 28 abr. 2024.
    • APA

      Avelar, A. M., Diniz, C., Camargo, F. de, Giovedi, C., Abe, A., Cherubini, M., et al. (2023). Best estimate plus uncertainty analysis of metal-water reaction transient experiment. Nuclear Engineering and Design, 411, 12 . doi:10.1016/j.nucengdes.2023.112414
    • NLM

      Avelar AM, Diniz C, Camargo F de, Giovedi C, Abe A, Cherubini M, Petruzzi A, Mourão MB. Best estimate plus uncertainty analysis of metal-water reaction transient experiment [Internet]. Nuclear Engineering and Design. 2023 ; 411 12 .[citado 2024 abr. 28 ] Available from: https://doi.org/10.1016/j.nucengdes.2023.112414
    • Vancouver

      Avelar AM, Diniz C, Camargo F de, Giovedi C, Abe A, Cherubini M, Petruzzi A, Mourão MB. Best estimate plus uncertainty analysis of metal-water reaction transient experiment [Internet]. Nuclear Engineering and Design. 2023 ; 411 12 .[citado 2024 abr. 28 ] Available from: https://doi.org/10.1016/j.nucengdes.2023.112414
  • Source: EPJ Nuclear Sciences & Technologies. Unidade: EP

    Subjects: REATORES NUCLEARES, SEGURANÇA NUCLEAR, CORROSÃO, IRRADIAÇÃO

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    • ABNT

      GOMES, Daniel de Souza et al. Evaluation of corrosion on the fuel performance of stainless steel cladding. EPJ Nuclear Sciences & Technologies, v. 2, n. 40, p. 1-6, 2016Tradução . . Disponível em: https://doi.org/10.1051/epjn/2016033. Acesso em: 28 abr. 2024.
    • APA

      Gomes, D. de S., Abe, A., Silva, A. T. e, Giovedi, C., & Martins, M. R. (2016). Evaluation of corrosion on the fuel performance of stainless steel cladding. EPJ Nuclear Sciences & Technologies, 2( 40), 1-6. doi:10.1051/epjn/2016033
    • NLM

      Gomes D de S, Abe A, Silva AT e, Giovedi C, Martins MR. Evaluation of corrosion on the fuel performance of stainless steel cladding [Internet]. EPJ Nuclear Sciences & Technologies. 2016 ; 2( 40): 1-6.[citado 2024 abr. 28 ] Available from: https://doi.org/10.1051/epjn/2016033
    • Vancouver

      Gomes D de S, Abe A, Silva AT e, Giovedi C, Martins MR. Evaluation of corrosion on the fuel performance of stainless steel cladding [Internet]. EPJ Nuclear Sciences & Technologies. 2016 ; 2( 40): 1-6.[citado 2024 abr. 28 ] Available from: https://doi.org/10.1051/epjn/2016033

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