Simulation of the System Dynamics for the Molten Salt Reactor Experiment Using Modified TRACE
International Conference on Nuclear Engineering (ICONE23)
2015
Simulation of Reactivity Initialized Transients at Different Power Levels for Molten Salt Reactor Using Modified TRACE
International Congress on Advances in Nuclear Power Plants (ICAPP 2015)
2015
Uncertainty and Sensitivity Analysis of the TALL-3D Experiment Using Thermal-Hydraulic Coupled Codes
International Congress on Advances in Nuclear Power Plants (ICAPP 2015)
2015
Preliminary Analysis of Basic Reactor Physics of the Dual Fluid Reactor
International Congress on Advances in Nuclear Power Plants (ICAPP 2015)
2015
Development of a Multi-Scale Thermal-Hydraulic Model of the TALL-3D Facility and Validation with Experimental Data,
International Congress on Advances in Nuclear Power Plants (ICAPP 2015)
2015
Multiscale Analysis of Forced and Natural Convection including Heat Transfer Phenomena in the TALL-3D Experimental Facility
The 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16)
2015
Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors
Nuclear Engineering and Design,
2015
281
22-38
Journal of Nuclear Materials, 465, Pages 260-267, June 2015. Numerical investigation of models for drag, lift, wall lubrication and turbulent dispersion forces for the simulation of gas-liquid two-phase flow
Chemical Engineering Research and Design
2015
17-35
Experimental investigation on the causes for pellet fragmentation under LOCA conditions
Journal of Nuclear Materials
2015
465
260-267