Difference between revisions of "SIG Nuclear / Publications"

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== Papers ==
 
== Papers ==
 
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<li> [http://dx.doi.org/] I. Clifford and H. Jasak. Application of Multi-Physics Methods to Spatial Reactor Dynamics. 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics (M&C), Saratoga Springs, NY, USA. May 3-7 2009.
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<li> [http://dx.doi.org/] I. Clifford and H. Jasak. Application of Multi-Physics Toolkit to Spatial Reactor Dynamics. 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics (M&C), Saratoga Springs, NY, USA. May 3-7 2009.
 
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<li> [http://www.aesj.or.jp/publication/pnst002/data/107-113.pdf] 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).  
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<li> [http://www.aesj.or.jp/publication/pnst002/data/107-113.pdf] 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).  
 
<li> [http://dx.doi.org/] I. Clifford, K. Ivanov and M. Avramova. A General Coarse and Fine Mesh Solution Scheme for Fluid Flow Modelling in VHTRs. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12. 2011.
 
<li> [http://dx.doi.org/] I. Clifford, K. Ivanov and M. Avramova. A General Coarse and Fine Mesh Solution Scheme for Fluid Flow Modelling in VHTRs. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12. 2011.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2011.04.021] V. R. Gopala et al. Development and validation of a CFD model predicting the backfill process of a nuclear waste gallery. Nuclear Engineering and Design, Vol. 241, pp 2508–2518, 2011.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2011.06.028] J. Xiong et al. Turbulence modeling for mass transfer enhancement by separation and reattachment with two-equation eddy-viscosity models. Nuclear Engineering and Design, Vol. 241, pp 3190–3200, 2011.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2011.08.011] M. Liu, , Y. Ishiwatari. Unsteady numerical simulations of the single-phase turbulent mixing between two channels connected by a narrow gap. Nuclear Engineering and Design, Vol. 241, pp 4194–4205, 2011.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2011.08.084] A. Gandhir, Y. Hassan. RANS modeling for flow in nuclear fuel bundle in pressurized water reactors (PWR). Nuclear Engineering and Design, Vol. 241, pp 4404–4408, 2011.
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<li> [http://www.nss.si/proc/nene2012/Publication_datoteke/Proceedings/405.pdf] B. Mikuz et al. OpenFOAM simulations of the Turbulent Flow in a Rod Bundle with Mixing Vanes. Proceedings of the 21st International Conference Nuclear Energy for New Europe, Ljubljana, 2012.
 
<li> [http://www.nss.si/proc/nene2012/Publication_datoteke/Proceedings/405.pdf] B. Mikuz et al. OpenFOAM simulations of the Turbulent Flow in a Rod Bundle with Mixing Vanes. Proceedings of the 21st International Conference Nuclear Energy for New Europe, Ljubljana, 2012.
 
<li> [http://dx.doi.org/] I. Clifford, K. Ivanov and M. Avramova. A Multiscale Homogenization and Reconstruction Approach for Solid Material Temperature Calculations in the MHTGR Core. Proceedings of the HTR 2012, Tokyo, Japan, October 28 – November 1. 2012.
 
<li> [http://dx.doi.org/] I. Clifford, K. Ivanov and M. Avramova. A Multiscale Homogenization and Reconstruction Approach for Solid Material Temperature Calculations in the MHTGR Core. Proceedings of the HTR 2012, Tokyo, Japan, October 28 – November 1. 2012.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2012.05.029] F. Roelofs et al. Simulating fuel assemblies with low resolution CFD approaches. Nuclear Engineering and Design, Vol. 250, pp 548-559, 2012.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2011.10.071] P. Nilsson et al. LES with acoustics and FSI for deforming plates in gas flow. Nuclear Engineering and Design, Vol. 253, pp 387-395, 2012.
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<li> [http://dx.doi.org/10.1016/j.compfluid.2013.10.001] 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).
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<li> [http://dx.doi.org/10.1016/j.compfluid.2013.10.001] A. Sakowitz et al. Effects of velocity ratio and inflow pulsations on the flow in a T-junction by Large Eddy Simulation. Computers & Fluids, Vol. 88, pp 374–385 (2013).
<li> [http://dx.doi.org/10.1016/j.nucengdes.2013.08.070] 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).
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2012.11.016] I. Clifford, K. Ivanov and M. Avramova. A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores. Nuclear Engineering and Design, Vol. 256, pp. 1–13, 2013.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2013.08.070] 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).
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2012.11.016] I. Clifford, K. Ivanov and M. Avramova. A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores. Nuclear Engineering and Design, Vol. 256, pp 1–13, 2013.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2012.11.008] M. Liu, , Y. Ishiwatari. Unsteady numerical simulations of single-phase turbulent mixing in tight lattice geometries. Nuclear Engineering and Design, Vol. 256, pp 28-37, 2013.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2013.02.030] B.L. Smith et al. A CFD benchmarking exercise based on flow mixing in a T-junction. Nuclear Engineering and Design, Vol. 264, pp 80–88, 2013.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2013.02.018] M. Naitoh et al. Evaluation method for pipe wall thinning due to liquid droplet impingement. Nuclear Engineering and Design, Vol. 264, pp 195-202, 2013.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2013.07.018] F. Roelofs et al. Review of fuel assembly and pool thermal hydraulics for fast reactors. Nuclear Engineering and Design, Vol. 265, pp 1205–1222, 2013.
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<li> [http://dx.doi.org/10.1016/j.anucene.2013.10.015] 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).
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<li> [http://dx.doi.org/10.1016/j.anucene.2013.12.019] 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).
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<li> [http://dx.doi.org/10.1016/j.anucene.2013.09.020] Q. Zeng, J. Cai. Three-dimension simulation of bubble behavior under nonlinear oscillation. Annals of Nuclear Energy, Vol. 63, pp 680–690, 2014.
<li> [http://dx.doi.org/10.14741/ijcet/spl.2.2014.82] 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).
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<li> [http://dx.doi.org/10.1016/j.anucene.2013.07.021] D. Nath, M. K. Verma. Numerical simulation of convection of argon gas in fast breeder reactor. Annals of Nuclear Energy, Vol. 63, pp 51-58, 2014.
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<li> [http://dx.doi.org/10.1016/j.anucene.2013.10.015] 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.
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<li> [http://dx.doi.org/10.1016/j.anucene.2013.12.019] 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.
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<li> [http://dx.doi.org/10.1016/j.anucene.2014.04.009] G. Patel et al. Numerical modelling of low-Reynolds number direct contact condensation in a suppression pool test facility. Annals of Nuclear Energy, Vol. 71, pp 376-387, 2014.
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<li> [http://dx.doi.org/10.14741/ijcet/spl.2.2014.82] 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.
 
<li> [http://www.etlibrary.org/?m=fbook&a=details&aid=14701] C. Tian et al. Numerical Simulation of Plume Motions for Cooling Tower in an Inland Nuclear Power Plant.  
 
<li> [http://www.etlibrary.org/?m=fbook&a=details&aid=14701] C. Tian et al. Numerical Simulation of Plume Motions for Cooling Tower in an Inland Nuclear Power Plant.  
Proceedings of the 2014 3rd International Conference on Informatics, Environment, Energy and Applications IPCBEE vol. 66 (2014).
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Proceedings of the 2014 3rd International Conference on Informatics, Environment, Energy and Applications IPCBEE vol. 66, 2014.
 
<li> [http://www.asmeconferences.org/icone22/] C. Fiorina et al. A time-dependent solver for coupled neutron-transport thermal-mechanics calculations and application to the simulation of the Godiva prompt-critical bursts. Proceedings of the 2014 22th International Conference on Nuclear Engineering ICONE22. July 7-11, 2014, Prague, Czech Republic.
 
<li> [http://www.asmeconferences.org/icone22/] C. Fiorina et al. A time-dependent solver for coupled neutron-transport thermal-mechanics calculations and application to the simulation of the Godiva prompt-critical bursts. Proceedings of the 2014 22th International Conference on Nuclear Engineering ICONE22. July 7-11, 2014, Prague, Czech Republic.
<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.08.002] M.S. Loginov et al. Towards the efficient turbulence closure for mixing phenomena in the core outlet of a nuclear reactor. Nuclear Engineering and Design, Vol. 278, pp. 472-480, 2014.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.01.014] J. Xiong, X. Cheng. Turbulence modelling for supercritical pressure heat transfer in upward tube flow. Nuclear Engineering and Design, Vol. 270, pp 249-258, 2014.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2013.12.017] G.J. Auwerda et al. Comparison of 2D and 3D heat transfer models around the coolant channels in the HTR-PM side reflector. Nuclear Engineering and Design, Vol. 271, pp 465-471, 2014.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.04.022] V. Geža et al. Computational and experimental studies of the flow field near the beam entrance window of a liquid metal target. Nuclear Engineering and Design, Vol. 275, pp 96–106, 2014.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.08.002] M.S. Loginov et al. Towards the efficient turbulence closure for mixing phenomena in the core outlet of a nuclear reactor. Nuclear Engineering and Design, Vol. 278, pp 472-480, 2014.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.03.008] J.R. Lee et al. Synthesis of the turbulent mixing in a rod bundle with vaned spacer grids based on the OECD-KAERI CFD benchmark exercise. Nuclear Engineering and Design, Vol. 279, pp 3–18, 2014.
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<li> [http://dx.doi.org/10.1016/j.compfluid.2014.02.013] E. Komen et al. Quasi-DNS capabilities of OpenFOAM for different mesh types. Computers & Fluids, Vol. 96, pp 87-104, 2014.
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<li> [http://www.sciencedirect.com/science/article/pii/S0009250914001146] M. Aufiero et al. Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis, Chemical Engineering Science Vol. 111,  pp 390–401, 2014.
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<li> [http://dx.doi.org/10.1016/j.pnucene.2014.05.019] J. De Amicis et al. Experimental and numerical study of the laminar flow in helically coiled pipes. Progress in Nuclear Energy Vol. 76, pp 206-215, 2014.
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<li> [http://dx.doi.org/] Authors. Title. Journal/Proceedings.  
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<li> [http://dx.doi.org/10.1016/j.anucene.2015.02.011] Y. Li et al. Effect of wall structure on pebble stagnation behavior in pebble bed reactor. Annals of Nuclear Energy, Vol. 80, pp 195-202, 2015.
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<li> [http://dx.doi.org/10.1016/j.anucene.2014.10.014] J. Leppänen et al. The Numerical Multi-Physics project (NUMPS) at VTT Technical Research Centre of Finland. Annals of Nuclear Energy Vol. 84, pp 55-62, 2014.
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<li> [http://dx.doi.org/10.1016/j.anucene.2015.01.037] K. Jareteg et al. Coupled fine-mesh neutronics and thermal-hydraulics – Modeling and implementation for PWR fuel assemblies. Annals of Nuclear Energy Vol. 84, pp 244-257, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.11.003] G. Bandini et al. Assessment of systems codes and their coupling with CFD codes in thermal–hydraulic applications to innovative reactors. Nuclear Engineering and Design Vol. 281, pp 22–38, 2015.
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<li> [http://www.sciencedirect.com/science/article/pii/S002954931500093X] A. K. Kansal et al. CFD analysis of moderator flow and temperature fields inside a vertical calandria vessel of nuclear reactor. Nuclear Engineering and Design Vol. 287, pp 95–107, 2015.
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<li> [http://dx.doi.org/10.1016/j.pnucene.2014.09.003] J. Kim, S.-W. Hong. Analysis of hydrogen flame acceleration in APR1400 containment by coupling hydrogen distribution and combustion analysis codes. Progress in Nuclear Energy Vol. 78, pp 101-109, 2015.
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<li> [http://dx.doi.org/10.1016/j.pnucene.2014.11.015] X. Chai et al. A new drag force model for the wake acceleration effect and its application to simulation of bubbly flow. Progress in Nuclear Energy Vol. 80, pp 24-36, 2015.
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<li> [http://dx.doi.org/10.1016/j.pnucene.2015.04.011] Q. Zeng et al. Numerical simulation of single bubble condensation in subcooled flow using OpenFOAM. Progress in Nuclear Energy Vol. 83, pp 336-346, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2015.04.036] E. J. Owoeye, D. Schubring. Numerical simulation of vapor bubble condensation in turbulent subcooled flow boiling. Nuclear Engineering and Design Vol. 289, pp 126-143, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2015.04.002] S. Abe et al. RANS analyses on erosion behavior of density stratification consisted of helium–air mixture gas by a low momentum vertical buoyant jet in the PANDA test facility, the third international benchmark exercise (IBE-3). Nuclear Engineering and Design Vol. 289, pp 231–239, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.11.007] X. Cheng et al. European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems. Nuclear Engineering and Design Vol. 290, pp 2-12, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.11.001] J. Pacio et al. Heat transfer to liquid metals in a hexagonal rod bundle with grid spacers: Experimental and simulation results. Nuclear Engineering and Design Vol. 290, pp 27–39, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.12.006] D. Pialla et al. Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project. Nuclear Engineering and Design Vol. 290, pp 78–86, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.11.006] F. Roelofs et al. Status and perspective of turbulence heat transfer modelling for the industrial application of liquid metal flows. Nuclear Engineering and Design Vol. 290, pp 99–106, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.11.009] A. Batta et al. Experimental and numerical investigation of liquid-metal free-surface flows in spallation targets. Nuclear Engineering and Design Vol. 290, pp 107–118, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2014.11.047] T. Barth et al. Particle deposition and resuspension in gas-cooled reactors—Activity overview of the two European research projects THINS and ARCHER. Nuclear Engineering and Design Vol. 290, pp 127–134, 2015.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2015.05.035] C. Fiorina et al. GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors. Nuclear Engineering and Design Vol. 294, pp 24-37, 2015.
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<li> [http://dx.doi.org/10.1016/j.fusengdes.2015.09.017] Q. He et al. Acceleration of the OpenFOAM-based MHD solver using graphics processing units. Fusion Engineering and Design Vol. 101, pp 88-93, 2015.
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<li> [http://dx.doi.org/10.1016/j.anucene.2015.08.004] H. Wu & Rizwan-uddin. A tightly coupled scheme for neutronics and thermal–hydraulics using open-source software. Annals of Nuclear Energy, Vol.  87, pp 16–22, 2016.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2015.12.021] B. Mikuž, & I. Tiselj. Wall-resolved Large Eddy Simulation in grid-free 5 × 5 rod bundle of MATiS-H experiment. Nuclear Engineering and Design, Vol. 298, pp 64–77, 2016.
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<li> [http://dx.doi.org/10.1016/j.pnucene.2016.02.004] N. Samkhaniani & M.R. Ansari. Numerical simulation of bubble condensation using CF-VOF. Progress in Nuclear Energy, Vol. 89, pp 120-131, 2016.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2016.03.006]    C. Peña-Monferrer et al. CFD modelling and validation of upward bubbly flow in an adiabatic vertical pipe using the quadrature method of moments. Nuclear Engineering and Design Vol. 301, Pages 320–332, 2016.
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<li> [http://dx.doi.org/10.1016/j.nucengdes.2017.02.010]        M. Ishigaki et al. Influence of mesh non-orthogonality on numerical simulation of buoyant jet flows. Nuclear Engineering and Design Vol. 314, pp 326–337, 2017.
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<li> [https://doi.org/10.1016/j.anucene.2017.05.059]        R. Sugrue et al. Assessment of a simplified set of momentum closure relations for low volume fraction regimes in STAR-CCM+ and OpenFOAM. Annals of Nuclear Energy Vol. 110, pp 79–87, 2017.
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<li> [https://doi.org/10.1016/j.nucengdes.2017.06.018]        M. Kumar et al. Investigations of natural convection and circulation in Passive Moderator Cooling System of an advanced reactor in a scaled test facility. Nuclear Engineering and Design Vol. 322, pp 55–67, 2017.
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<li> [https://doi.org/10.1016/j.anucene.2018.04.037] A. Arkoma et al. Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage, Annals of Nuclear Energy Vol. 119, pp 129-138, 2018.
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<li> [https://doi.org/10.1016/j.anucene.2018.05.034] A. Alali et al. Numerical investigations on the coupling of the one-group interfacial area transport equation and subcooled boiling models for nuclear safety applications, Annals of Nuclear Energy Vol. 120, pp 155-168, 2018.
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<li> [https://doi.org/10.1016/j.nucengdes.2018.01.049] A. Shams et al. Synthesis of a CFD benchmarking exercise for a T-junction with wall, Nuclear Engineering and Design Vol. 330, pp 199-216, 2018.<br />
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<li> [https://doi.org/10.1016/j.anucene.2018.01.021] V. Vasconcelos et al. Coupled unstructured fine-mesh neutronics and thermal-hydraulics methodology using open software: A proof-of-concept, Annals of Nuclear Energy Vol. 115, pp 173-185, 2018.<br />
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<li> [https://doi.org/10.1016/j.anucene.2018.07.036] Rodrigo G.G.de Oliveira et KonstantinMikityuk. Analytical solutions to a coupled fluid dynamics and neutron transport problem with application to GeN-Foam verification, Annals of Nuclear Energy Vol. 121, pp 446-451, 2018.<br />
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<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://dx.doi.org/] I. Clifford. Multi-Scale Modeling of Very High Temperature Reactor Thermal-Fluids Using OpenFOAM. 6th OpenFOAM Workshop, PennState University, USA. March 2011.
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<li> [http://www.personal.psu.edu/dab143/OFW6/Presentations/ivor_clifford_slides.pdf] I. Clifford. Multi-Scale Modeling of Very High Temperature Reactor Thermal-Fluids Using OpenFOAM. 6th OpenFOAM Workshop, PennState University, USA. March 2011.
 
13-16 June, 2011
 
13-16 June, 2011
 
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<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.
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<li> [http://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW9_2014_Zagreb/Abstracts/Klas_Jareteg_OFW09_EA_0056.pdf] K. Jareteg. Multiphysics simulations of Light Water Reactors using OpenFOAM, presented at the [http://www.openfoamworkshop.org/ 9th OpenFOAM Workshop] in Zagreb, June 2014. ([http://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW9_2014_Zagreb/Presentations/Klas_Jareteg_OFW09_P_0056.pdf slides])
<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.
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<li> [http://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW9_2014_Zagreb/Abstracts/Ivor_Clifford_OFW09_EA_0002.pdf] 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. ([http://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW9_2014_Zagreb/Presentations/Ivor_Clifford_OFW09_P_0002.zip slides])
<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.
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<li> [http://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW9_2014_Zagreb/Abstracts/Joachim_Herb_OFW09_EA_0011.pdf] 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. ([http://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW9_2014_Zagreb/Presentations/Joachim_Herb_OFW09_P_0011.pdf slides])
<li> [http://registration.sdewes.org/ofw09/dfile.php?dm=Pxeeb5579a74c9c158901fdbd6bf5e1883a7cab215x2] C. Fiorina et al.  
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<li> [http://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW9_2014_Zagreb/Abstracts/Carlo_Fiorina_OFW09_EA_0023.pdf] C. Fiorina et al.  
Development plans and first steps for a multi-physics platform for nuclear reactor analysis, presented at the [http://www.openfoamworkshop.org/2014/ 9th OpenFOAM Workshop] in Zagreb, June 2014.
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Development plans and first steps for a multi-physics platform for nuclear reactor analysis, presented at the [http://www.openfoamworkshop.org/2014/ 9th OpenFOAM Workshop] in Zagreb, June 2014. ([http://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW9_2014_Zagreb/Presentations/Carlo_Fiorina_OFW09_P_0023.pdf slides])
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<li> [https://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW11_2016_Guimaraes/files/papers/OFW11_paper_40.pdf/download] C. Fiorina. GeN-Foam: an OpenFOAM based multi-physics solver for nuclear reactor analysis, presented at the [http://openfoam-extend.sourceforge.net/OpenFOAM_Workshops/OFW11_2016_Guimaraes/ 11th OpenFOAM Workshop] in Guimarães, Portugal, June 2016. ([https://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW11_2016_Guimaraes/files/slides/OFWP040.pdf/download slides])
 +
<li> [https://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW11_2016_Guimaraes/files/papers/OFW11_paper_29.pdf/download] J. Herb, F. Chiriac. One- and Two-Phase Coupling of OpenFOAM with the Thermal-Hydraulic Code ATHLET for Nuclear Safety Analyses, presented at the [http://openfoam-extend.sourceforge.net/OpenFOAM_Workshops/OFW11_2016_Guimaraes/ 11th OpenFOAM Workshop] in Guimarães, Portugal, June 2016. ([https://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW11_2016_Guimaraes/files/slides/OFWP029.pdf/download slides])
 +
<li> [https://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW11_2016_Guimaraes/files/papers/OFW11_paper_110.pdf/download] M. Tano Retamales, P. Rubiolo, O. Doche. Development and Implementation of an Adapted Turbulent Model in OpenFOAM, presented at the [http://openfoam-extend.sourceforge.net/OpenFOAM_Workshops/OFW11_2016_Guimaraes/ 11th OpenFOAM Workshop] in Guimarães, Portugal, June 2016. ([https://sourceforge.net/projects/openfoam-extend/files/OpenFOAM_Workshops/OFW11_2016_Guimaraes/files/slides/OFWP110.pdf/download slides])
 
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Latest revision as of 22:45, 26 August 2018

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

1 Papers

  • [1] I. Clifford and H. Jasak. Application of Multi-Physics Toolkit to Spatial Reactor Dynamics. 2009 International Conference on Advances in Mathematics, Computational Methods, and Reactor Physics (M&C), Saratoga Springs, NY, USA. May 3-7 2009.


  • [2] I. Clifford and K. Ivanov. PBMR 400MW Benchmark Calculations Using the Simplified P3 Approach. Proceedings of HTR 2010, Prague, Czech Republic, October 18-20. 2010.


  • [3] 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).
  • [4] I. Clifford, K. Ivanov and M. Avramova. A General Coarse and Fine Mesh Solution Scheme for Fluid Flow Modelling in VHTRs. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, Brazil, May 8-12. 2011.
  • [5] V. R. Gopala et al. Development and validation of a CFD model predicting the backfill process of a nuclear waste gallery. Nuclear Engineering and Design, Vol. 241, pp 2508–2518, 2011.
  • [6] J. Xiong et al. Turbulence modeling for mass transfer enhancement by separation and reattachment with two-equation eddy-viscosity models. Nuclear Engineering and Design, Vol. 241, pp 3190–3200, 2011.
  • [7] M. Liu, , Y. Ishiwatari. Unsteady numerical simulations of the single-phase turbulent mixing between two channels connected by a narrow gap. Nuclear Engineering and Design, Vol. 241, pp 4194–4205, 2011.
  • [8] A. Gandhir, Y. Hassan. RANS modeling for flow in nuclear fuel bundle in pressurized water reactors (PWR). Nuclear Engineering and Design, Vol. 241, pp 4404–4408, 2011.


  • [9] B. Mikuz et al. OpenFOAM simulations of the Turbulent Flow in a Rod Bundle with Mixing Vanes. Proceedings of the 21st International Conference Nuclear Energy for New Europe, Ljubljana, 2012.
  • [10] I. Clifford, K. Ivanov and M. Avramova. A Multiscale Homogenization and Reconstruction Approach for Solid Material Temperature Calculations in the MHTGR Core. Proceedings of the HTR 2012, Tokyo, Japan, October 28 – November 1. 2012.
  • [11] F. Roelofs et al. Simulating fuel assemblies with low resolution CFD approaches. Nuclear Engineering and Design, Vol. 250, pp 548-559, 2012.
  • [12] P. Nilsson et al. LES with acoustics and FSI for deforming plates in gas flow. Nuclear Engineering and Design, Vol. 253, pp 387-395, 2012.


  • [13] A. Sakowitz et al. Effects of velocity ratio and inflow pulsations on the flow in a T-junction by Large Eddy Simulation. Computers & Fluids, Vol. 88, pp 374–385 (2013).
  • [14] 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).
  • [15] I. Clifford, K. Ivanov and M. Avramova. A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores. Nuclear Engineering and Design, Vol. 256, pp 1–13, 2013.
  • [16] M. Liu, , Y. Ishiwatari. Unsteady numerical simulations of single-phase turbulent mixing in tight lattice geometries. Nuclear Engineering and Design, Vol. 256, pp 28-37, 2013.
  • [17] B.L. Smith et al. A CFD benchmarking exercise based on flow mixing in a T-junction. Nuclear Engineering and Design, Vol. 264, pp 80–88, 2013.
  • [18] M. Naitoh et al. Evaluation method for pipe wall thinning due to liquid droplet impingement. Nuclear Engineering and Design, Vol. 264, pp 195-202, 2013.
  • [19] F. Roelofs et al. Review of fuel assembly and pool thermal hydraulics for fast reactors. Nuclear Engineering and Design, Vol. 265, pp 1205–1222, 2013.


  • [20] Q. Zeng, J. Cai. Three-dimension simulation of bubble behavior under nonlinear oscillation. Annals of Nuclear Energy, Vol. 63, pp 680–690, 2014.
  • [21] D. Nath, M. K. Verma. Numerical simulation of convection of argon gas in fast breeder reactor. Annals of Nuclear Energy, Vol. 63, pp 51-58, 2014.
  • [22] 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.
  • [23] 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.
  • [24] G. Patel et al. Numerical modelling of low-Reynolds number direct contact condensation in a suppression pool test facility. Annals of Nuclear Energy, Vol. 71, pp 376-387, 2014.
  • [25] 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.
  • [26] C. Tian et al. Numerical Simulation of Plume Motions for Cooling Tower in an Inland Nuclear Power Plant. Proceedings of the 2014 3rd International Conference on Informatics, Environment, Energy and Applications IPCBEE vol. 66, 2014.
  • [27] C. Fiorina et al. A time-dependent solver for coupled neutron-transport thermal-mechanics calculations and application to the simulation of the Godiva prompt-critical bursts. Proceedings of the 2014 22th International Conference on Nuclear Engineering ICONE22. July 7-11, 2014, Prague, Czech Republic.
  • [28] J. Xiong, X. Cheng. Turbulence modelling for supercritical pressure heat transfer in upward tube flow. Nuclear Engineering and Design, Vol. 270, pp 249-258, 2014.
  • [29] G.J. Auwerda et al. Comparison of 2D and 3D heat transfer models around the coolant channels in the HTR-PM side reflector. Nuclear Engineering and Design, Vol. 271, pp 465-471, 2014.
  • [30] V. Geža et al. Computational and experimental studies of the flow field near the beam entrance window of a liquid metal target. Nuclear Engineering and Design, Vol. 275, pp 96–106, 2014.
  • [31] M.S. Loginov et al. Towards the efficient turbulence closure for mixing phenomena in the core outlet of a nuclear reactor. Nuclear Engineering and Design, Vol. 278, pp 472-480, 2014.
  • [32] J.R. Lee et al. Synthesis of the turbulent mixing in a rod bundle with vaned spacer grids based on the OECD-KAERI CFD benchmark exercise. Nuclear Engineering and Design, Vol. 279, pp 3–18, 2014.
  • [33] E. Komen et al. Quasi-DNS capabilities of OpenFOAM for different mesh types. Computers & Fluids, Vol. 96, pp 87-104, 2014.
  • [34] M. Aufiero et al. Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis, Chemical Engineering Science Vol. 111, pp 390–401, 2014.
  • [35] J. De Amicis et al. Experimental and numerical study of the laminar flow in helically coiled pipes. Progress in Nuclear Energy Vol. 76, pp 206-215, 2014.


  • [36] Y. Li et al. Effect of wall structure on pebble stagnation behavior in pebble bed reactor. Annals of Nuclear Energy, Vol. 80, pp 195-202, 2015.
  • [37] J. Leppänen et al. The Numerical Multi-Physics project (NUMPS) at VTT Technical Research Centre of Finland. Annals of Nuclear Energy Vol. 84, pp 55-62, 2014.
  • [38] K. Jareteg et al. Coupled fine-mesh neutronics and thermal-hydraulics – Modeling and implementation for PWR fuel assemblies. Annals of Nuclear Energy Vol. 84, pp 244-257, 2015.
  • [39] G. Bandini et al. Assessment of systems codes and their coupling with CFD codes in thermal–hydraulic applications to innovative reactors. Nuclear Engineering and Design Vol. 281, pp 22–38, 2015.
  • [40] A. K. Kansal et al. CFD analysis of moderator flow and temperature fields inside a vertical calandria vessel of nuclear reactor. Nuclear Engineering and Design Vol. 287, pp 95–107, 2015.
  • [41] J. Kim, S.-W. Hong. Analysis of hydrogen flame acceleration in APR1400 containment by coupling hydrogen distribution and combustion analysis codes. Progress in Nuclear Energy Vol. 78, pp 101-109, 2015.
  • [42] X. Chai et al. A new drag force model for the wake acceleration effect and its application to simulation of bubbly flow. Progress in Nuclear Energy Vol. 80, pp 24-36, 2015.
  • [43] Q. Zeng et al. Numerical simulation of single bubble condensation in subcooled flow using OpenFOAM. Progress in Nuclear Energy Vol. 83, pp 336-346, 2015.
  • [44] E. J. Owoeye, D. Schubring. Numerical simulation of vapor bubble condensation in turbulent subcooled flow boiling. Nuclear Engineering and Design Vol. 289, pp 126-143, 2015.
  • [45] S. Abe et al. RANS analyses on erosion behavior of density stratification consisted of helium–air mixture gas by a low momentum vertical buoyant jet in the PANDA test facility, the third international benchmark exercise (IBE-3). Nuclear Engineering and Design Vol. 289, pp 231–239, 2015.
  • [46] X. Cheng et al. European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems. Nuclear Engineering and Design Vol. 290, pp 2-12, 2015.
  • [47] J. Pacio et al. Heat transfer to liquid metals in a hexagonal rod bundle with grid spacers: Experimental and simulation results. Nuclear Engineering and Design Vol. 290, pp 27–39, 2015.
  • [48] D. Pialla et al. Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project. Nuclear Engineering and Design Vol. 290, pp 78–86, 2015.
  • [49] F. Roelofs et al. Status and perspective of turbulence heat transfer modelling for the industrial application of liquid metal flows. Nuclear Engineering and Design Vol. 290, pp 99–106, 2015.
  • [50] A. Batta et al. Experimental and numerical investigation of liquid-metal free-surface flows in spallation targets. Nuclear Engineering and Design Vol. 290, pp 107–118, 2015.
  • [51] T. Barth et al. Particle deposition and resuspension in gas-cooled reactors—Activity overview of the two European research projects THINS and ARCHER. Nuclear Engineering and Design Vol. 290, pp 127–134, 2015.
  • [52] C. Fiorina et al. GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors. Nuclear Engineering and Design Vol. 294, pp 24-37, 2015.
  • [53] Q. He et al. Acceleration of the OpenFOAM-based MHD solver using graphics processing units. Fusion Engineering and Design Vol. 101, pp 88-93, 2015.


  • [54] H. Wu & Rizwan-uddin. A tightly coupled scheme for neutronics and thermal–hydraulics using open-source software. Annals of Nuclear Energy, Vol. 87, pp 16–22, 2016.
  • [55] B. Mikuž, & I. Tiselj. Wall-resolved Large Eddy Simulation in grid-free 5 × 5 rod bundle of MATiS-H experiment. Nuclear Engineering and Design, Vol. 298, pp 64–77, 2016.
  • [56] N. Samkhaniani & M.R. Ansari. Numerical simulation of bubble condensation using CF-VOF. Progress in Nuclear Energy, Vol. 89, pp 120-131, 2016.
  • [57] C. Peña-Monferrer et al. CFD modelling and validation of upward bubbly flow in an adiabatic vertical pipe using the quadrature method of moments. Nuclear Engineering and Design Vol. 301, Pages 320–332, 2016.


  • [58] M. Ishigaki et al. Influence of mesh non-orthogonality on numerical simulation of buoyant jet flows. Nuclear Engineering and Design Vol. 314, pp 326–337, 2017.
  • [59] R. Sugrue et al. Assessment of a simplified set of momentum closure relations for low volume fraction regimes in STAR-CCM+ and OpenFOAM. Annals of Nuclear Energy Vol. 110, pp 79–87, 2017.
  • [60] M. Kumar et al. Investigations of natural convection and circulation in Passive Moderator Cooling System of an advanced reactor in a scaled test facility. Nuclear Engineering and Design Vol. 322, pp 55–67, 2017.


  • [61] A. Arkoma et al. Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage, Annals of Nuclear Energy Vol. 119, pp 129-138, 2018.
  • [62] A. Alali et al. Numerical investigations on the coupling of the one-group interfacial area transport equation and subcooled boiling models for nuclear safety applications, Annals of Nuclear Energy Vol. 120, pp 155-168, 2018.
  • [63] A. Shams et al. Synthesis of a CFD benchmarking exercise for a T-junction with wall, Nuclear Engineering and Design Vol. 330, pp 199-216, 2018.
  • [64] V. Vasconcelos et al. Coupled unstructured fine-mesh neutronics and thermal-hydraulics methodology using open software: A proof-of-concept, Annals of Nuclear Energy Vol. 115, pp 173-185, 2018.
  • [65] Rodrigo G.G.de Oliveira et KonstantinMikityuk. Analytical solutions to a coupled fluid dynamics and neutron transport problem with application to GeN-Foam verification, Annals of Nuclear Energy Vol. 121, pp 446-451, 2018.



  • [66] Authors. Title, Journal/Proceedings.

2 Slides

  • [67] 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.


  • [68] I. Clifford. The OpenFOAM Framework as a Tool for Pebble-Bed Multi-Physics Analysis. PHYSOR 2010 Workshop on Reactor Physics and Design of Next Build Reactors, May 14. 2010.


  • [69] 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.
  • [70] I. Clifford. Multi-Scale Modeling of Very High Temperature Reactor Thermal-Fluids Using OpenFOAM. 6th OpenFOAM Workshop, PennState University, USA. March 2011. 13-16 June, 2011


  • [71] K. Jareteg. Coupled calculations in OpenFOAM - Multiphysics handling, structures and solvers, presented at the Gothenburg Region OpenFOAM User Group Meeting, November 2012.


  • [72] K. Jareteg. Multiphysics simulations of Light Water Reactors using OpenFOAM, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014. (slides)
  • [73] 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. (slides)
  • [74] J. Herb. Coupling of OpenFOAM with Thermo-Hydraulic Simulation Code ATHLET, presented at the 9th OpenFOAM Workshop in Zagreb, June 2014. (slides)
  • [75] 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. (slides)


  • [76] C. Fiorina. GeN-Foam: an OpenFOAM based multi-physics solver for nuclear reactor analysis, presented at the 11th OpenFOAM Workshop in Guimarães, Portugal, June 2016. (slides)
  • [77] J. Herb, F. Chiriac. One- and Two-Phase Coupling of OpenFOAM with the Thermal-Hydraulic Code ATHLET for Nuclear Safety Analyses, presented at the 11th OpenFOAM Workshop in Guimarães, Portugal, June 2016. (slides)
  • [78] M. Tano Retamales, P. Rubiolo, O. Doche. Development and Implementation of an Adapted Turbulent Model in OpenFOAM, presented at the 11th OpenFOAM Workshop in Guimarães, Portugal, June 2016. (slides)


3 Posters

4 Thesis

  • [81] I. Clifford. Object-oriented multi-physics applied to spatial reactor dynamics. North West University. November 2007.


  • [82] E. Michta. Modeling of Subcooled Nucleate Boiling with OpenFOAM. KTH Royal Institute of Technology, Stockholm. February 2011.
  • [83] T. Bakx. Testing a Nuclear Pebble-Bed Reactor Model in OpenFOAM. Delft University of Technology. August 2011.


  • [84] R. Pegonen. Investigation of Thermal Mixing Using OpenFOAM. KTH Royal Institute of Technology, Stockholm. June 2012.
  • [85] F. A. Ettner. Efficient numerical simulation of the deflagration-to-detonation transition. Technische Universität München. October 2012.


  • [86] 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.
  • [87] I. Clifford. A hybrid coarse and fine mesh solution method for prismatic high temperature reactor thermal-fluid analysis. The Pennsylvania State University. May 2013.


  • [88] Authors. Title. University. Month 20xx.


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