Transient heat transfer analysis up to dryout in 3D fuel rods under unideal conditions through the development of a computer code

Authors

  • Rodolfo Ienny Martins Instituto de Engenharia Nuclear
  • Maria de Lourdes Moreira Instituto de Engenharia Nuclear
  • Paulo Augusto Berquó DeSampaio Instituto de Engenharia Nuclear
  • Renato Raoni Werneck Affonso Instituto de Engenharia Nuclear

Keywords:

3D Transient heat transfer, Fuel Rod, Finite Element, PWR

Abstract

In this report we present analyzes of the behavior of temperature in fuel rods with concentric fuel and perfect cladding, curved, and with dislocated fuel, through the development of a computer code.

References

MARTINS, R. I. Desenvolvimento de código computacional para análise de transferência de calor transiente 3D até o Dryout em varetas combustíveis sob condições não usuais. 2016, 183 f. Dissertação (Mestrado em Ciências e Tecnologias Nucleares)- Programa de Pós graduação em Ciência e Tecnologia Nucleares do Instituto de Engenharia Nuclear da Comissão Nacional de Energia Nuclear, Rio de Janeiro, nov. 2016.

MARTINS, R. I. et al.Transient heat transfer analysis up to dryout in 3D fuel rods under unideal conditions through the development of a computer code. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, - ENFIR - Meeting on Nuclear Reactor Physics and Thermal Hydraulics, 10., 2017, Belo Horizonte. Anais… Rio de Janeiro: ABEN, 2017. Não paginado.

COLL, A. et al. ELaSSCo: post-processing and visualization platform for distributed results. In: CONVENTION ON ADVANCES AND APPLICATIONS OF GID, 8., 2016, Barcelona. Anais… Barcelona: CIMNE, 2016. Não paginado. Disponível em: <http://www.gidhome.com> Acesso em: 29 Jun. 2016.

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Published

2021-07-08

How to Cite

Martins, R. I., Moreira, M. de L., DeSampaio, P. A. B., & Affonso, R. R. W. (2021). Transient heat transfer analysis up to dryout in 3D fuel rods under unideal conditions through the development of a computer code. Instituto De Engenharia Nuclear: Progress Report, (3), 102. Retrieved from https://revistas.ien.gov.br/index.php/ienprogressreport/article/view/287

Issue

Section

Engineering and Reactor Safety