Difference between revisions of "SIG Nuclear / Publications"

From OpenFOAMWiki
Line 24: Line 24:
 
<li> [http://virtual.vtt.fi/virtual/safir2010/vasenpalkki/finalseminar/Presentations/Thursday/Area_4/NuFoam_SAFIR2010.pdf] J. Peltola et al. Adaptation and validation of
 
<li> [http://virtual.vtt.fi/virtual/safir2010/vasenpalkki/finalseminar/Presentations/Thursday/Area_4/NuFoam_SAFIR2010.pdf] 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.
 
OpenFOAM® CFD-solvers for nuclear safety related flow simulations, presented at the SAFIR2010 Seminar, Espoo, March 2011.
<li> [http://www.modlab.lv/docs/2011/OpenFOAM/Invited_Presentations_R_Mukin.pdf] R. Mukin. Diffusion Inertia Model for Simulation Multiphase Turbulent Flows and implementation into OpenFOAM, presented at the [http://www.openfoamworkshop.org/2014/ 9th OpenFOAM Workshop] in Zagreb, June 2014.
 
  
  
 
<li> [http://klas.nephy.chalmers.se/publications/presentations/KlasJareteg-OF-GBG-Web.pdf] K. Jareteg. Coupled calculations in OpenFOAM - Multiphysics handling, structures and solvers, presented at the Gothenburg Region OpenFOAM User Group Meeting, November 2012.
 
<li> [http://klas.nephy.chalmers.se/publications/presentations/KlasJareteg-OF-GBG-Web.pdf] K. Jareteg. Coupled calculations in OpenFOAM - Multiphysics handling, structures and solvers, presented at the Gothenburg Region OpenFOAM User Group Meeting, November 2012.
  
<li> [http://dx.doi.org/] Klas Jareteg. Multiphysics simulations of Light Water Reactors using OpenFOAM, presented at the [http://www.openfoamworkshop.org/ 9th OpenFOAM Workshop] in Zagreb, June 2014.
+
<li> [http://dx.doi.org/] K. Jareteg. Multiphysics simulations of Light Water Reactors using OpenFOAM, presented at the [http://www.openfoamworkshop.org/ 9th OpenFOAM Workshop] in Zagreb, June 2014.
 
<li> [http://registration.sdewes.org/ofw09/dfile.php?dm=Pxfa78bf8889b66c4f3f257b4c68c1fbb541157860x3] I. Clifford et al. A Hierarchical Multi-scale Approach to Modelling Heat Conduction in Prismatic HTGRs using OpenFOAM , presented at the [http://www.openfoamworkshop.org/ 9th OpenFOAM Workshop] in Zagreb, June 2014.
 
<li> [http://registration.sdewes.org/ofw09/dfile.php?dm=Pxfa78bf8889b66c4f3f257b4c68c1fbb541157860x3] I. Clifford et al. A Hierarchical Multi-scale Approach to Modelling Heat Conduction in Prismatic HTGRs using OpenFOAM , presented at the [http://www.openfoamworkshop.org/ 9th OpenFOAM Workshop] in Zagreb, June 2014.
 
<li> [http://registration.sdewes.org/ofw09/dfile.php?dm=Pxe3ef290aa5b1ab98749e0beb1e53b45b80fecaf2x2] J. Herb. Coupling of OpenFOAM with Thermo-Hydraulic Simulation Code ATHLET, presented at the [http://www.openfoamworkshop.org/2014/ 9th OpenFOAM Workshop] in Zagreb, June 2014.
 
<li> [http://registration.sdewes.org/ofw09/dfile.php?dm=Pxe3ef290aa5b1ab98749e0beb1e53b45b80fecaf2x2] J. Herb. Coupling of OpenFOAM with Thermo-Hydraulic Simulation Code ATHLET, presented at the [http://www.openfoamworkshop.org/2014/ 9th OpenFOAM Workshop] in Zagreb, June 2014.

Revision as of 11:38, 1 July 2014

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

1 Papers

  • [1] J. Cai, T. Watanabe. Numerical Simulation of Thermal Stratification in Cold Legs by Using OpenFOAM. Progress in NUCLEAR SCIENCE and TECHNOLOGY, Vol. 2, pp.107-113 (2011).
  • [2] 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).
  • [3] 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).
  • [4] 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).
  • [5] 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).
  • [6] 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).


  • [7] Authors. Title. Journal/Proceedings.

    2 Slides

    • [8] 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.
    • [9] 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.
    • [10] K. Jareteg. Coupled calculations in OpenFOAM - Multiphysics handling, structures and solvers, presented at the Gothenburg Region OpenFOAM User Group Meeting, November 2012.
    • [11] K. Jareteg. Multiphysics simulations of Light Water Reactors using OpenFOAM, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014.
    • [12] 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.
    • [13] J. Herb. Coupling of OpenFOAM with Thermo-Hydraulic Simulation Code ATHLET, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014.
    • [14] 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.
    • [15] Authors. Title, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014.

    3 Posters

    4 Thesis

    • [17] E. Michta. Modeling of Subcooled Nucleate Boiling with OpenFOAM. KTH Royal Institute of Technology, Stockholm. February 2011.
    • [18] T. Bakx. Testing a Nuclear Pebble-Bed Reactor Model in OpenFOAM. Delft University of Technology. August 2011.
    • [19] 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.
    • [20] Authors. Title. University. Month 20xx.


    Back to Sig Nuclear