Computational Fluid Dynamics Applied to Study Coolant Loss Regimes in Very High Temperature Reactors

Authors

  • Uebert Gonçalves Moreira Universidade Estadual de Santa Cruz - UESC
  • Dany Sanchez Dominguez Universidade Estadual de Santa Cruz - UESC
  • Leorlen Yunier Rojas Mazaira Universidade Federal de Pernambuco -UFPE
  • Carlos Alberto Brayner de Oliveira Lira Universidade Federal de Pernambuco -UFPE
  • Carlos Rafael García Henández Instituto Superior de Tecnologías y Ciencias Aplicadas - InSTEC

DOI:

https://doi.org/10.15392/bjrs.v9i2A.683

Keywords:

VHTR, Pebble Bed Reactor, CFD

Abstract

The nuclear energy is a good alternative to meet the continuous increase in world energy demand. In this pers-pective, VHTRs (Very High Temperature Reactors) are serious candidates for energy generation due to its   inherently safe performance, low power density and high conversion efficiency. However, the viability of these reactors depends on an efficient safety system in the operation of nuclear plants. The HTR (High Temperature Reactor)-10 model, an experimental reactor of the pebble bed type, is used as a case study in this work to perform the thermohydraulic simulation. Due to the complex patterns flow that appear in the pebble bed reactor core CFD (Computational Fluid Dynamics) techniques are used to simulate these reactors. A realistic approach is adopted to simulate the central annular column of the reactor core. As geometrical model of the fuel elements was selected the BCC (Body Centered Cubic) arrangement. Parameters considered for reactor design are available in the technical report of benchmark issues by IAEA (TECDOC-1694). We obtain the temperature profile distribution in the core for regimes where the coolant flow rate is smaller than recommended in a normal operation. In general, the temperature distributions calculated are consistent with phenomenological behavior. Even without considering the reactivity changes to reduce the reactor power or other safety mechanisms, the maximum temperatures do not exceed the recommended limits for TRISO fuel elements.

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Author Biographies

Uebert Gonçalves Moreira, Universidade Estadual de Santa Cruz - UESC

Departamento de Ciências Exatas e Tecnológicas

Dany Sanchez Dominguez, Universidade Estadual de Santa Cruz - UESC

Departamento de Ciências Exatas e Tecnológicas

Leorlen Yunier Rojas Mazaira, Universidade Federal de Pernambuco -UFPE

Departamento de Energia Nuclear

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Published

2021-07-24

How to Cite

Moreira, U. G., Dominguez, D. S., Mazaira, L. Y. R., Lira, C. A. B. de O., & Henández, C. R. G. (2021). Computational Fluid Dynamics Applied to Study Coolant Loss Regimes in Very High Temperature Reactors. Brazilian Journal of Radiation Sciences, 9(2A (Suppl.). https://doi.org/10.15392/bjrs.v9i2A.683

Issue

Section

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

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