Development of a 3D computer code for studies on heat transfer fuel rods in unusual situations

M. L. Moreira; P. A. B. Sampaio; R. R. W. Affonso

Development of a 3D computer code for studies on heat transfer fuel rods in unusual situations

Autores

M. L. Moreira
P. A. B. Sampaio
R. R. W. Affonso

Palavras-chave:

nuclear reactor, fuel rod, nuclear fuel, finite element method, heat transfer, accident analysis

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Como Citar

Moreira, M. L., Sampaio, P. A. B., & Affonso, R. R. W. (2015). Development of a 3D computer code for studies on heat transfer fuel rods in unusual situations. Instituto De Engenharia Nuclear: Progress Report, (1), 26. Recuperado de https://revistas.ien.gov.br/index.php/ienprogressreport/article/view/111