SIG Nuclear / Publications

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Here you can add links (or references) to publications with OpenFOAM for nuclear applications.

1 Papers

  • [1] A. Sakowitz et al. Effects of velocity ratio and inflow pulsations on the flow in a T-junction by Large Eddy Simulation. Annals of Nuclear Energy, Vol. 68, pp. 247–256 (2013).
  • [2] H. Wilkening, L. Ammirabile. Simulation of helium release in the Battelle Model Containment facility using OpenFOAM. Nuclear Engineering and Design, Vol. 265, pp. 402– 410 (2013).
  • [3] M. Aufiero et al. Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches. Annals of Nuclear Energy, Vol. 65, pp. 78–90 (2014).
  • [4] K. Jareteg et al. Fine-mesh deterministic modeling of PWR fuel assemblies: Proof-of-principle of coupled neutronic/thermal–hydraulic calculations. Annals of Nuclear Energy, Vol. 68, pp. 247–256 (2014).
  • [5] G. Harikrishnan et al. CFD Simulation of Subcooled Flow Boiling using OpenFOAM. International Journal of Current Engineering and Technology, Special Issue-2, pp. 441-447 2014.


  • [6] Authors. Title. Journal/Proceedings. Comment.

    2 Slides

    • [7] E. Mas de les Valls, L. Batet. OpenFOAM capabilities for MHD simulation under nuclear fusion technology conditions, presented at the 3rd OpenFOAM Workshop in Milan, July 2008.
    • [8] J. Peltola et al. Adaptation and validation of OpenFOAM® CFD-solvers for nuclear safety related flow simulations, presented at the SAFIR2010 Seminar, Espoo, March 2011.
  • [9] K. Jareteg. Coupled calculations in OpenFOAM - Multiphysics handling, structures and solvers, presented at the Gothenburg Region OpenFOAM User Group Meeting, November 2012.
  • [10] Klas Jareteg. Multiphysics simulations of Light Water Reactors using OpenFOAM, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014.
  • [11] I. Clifford et al. A Hierarchical Multi-scale Approach to Modelling Heat Conduction in Prismatic HTGRs using OpenFOAM , presented at the 9th OpenFOAM Workshop in Zagreb, June 2014.
  • [12] J. Herb. Coupling of OpenFOAM with Thermo-Hydraulic Simulation Code ATHLET, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014.
  • [13] C. Fiorina et al. Development plans and first steps for a multi-physics platform for nuclear reactor analysis, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014.
  • [14] Authors. Title, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014. </ul> </ul>

    3 Posters

    4 Thesis

    • [16] E. Michta. Modeling of Subcooled Nucleate Boiling with OpenFOAM. KTH Royal Institute of Technology, Stockholm. February 2011.
    • [17] T. Bakx. Testing a Nuclear Pebble-Bed Reactor Model in OpenFOAM. Delft University of Technology. August 2011.
    • [18] A. Alali. Development and validation of new solver based on the interfacial area transport equation for the numerical simulation of sub-cooled boiling with OpenFOAM CFD code for nuclear safety applications. Technische Universität München. August 2013.
    • [19] Authors. Title. University. Month 20xx.


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