| Finite volume methods, unstructured meshes and strict stability for hyperbolic problems J Nordström, K Forsberg, C Adamsson, P Eliasson Applied Numerical Mathematics 45 (4), 453-473, 2003 | 141 | 2003 |
| Influence of axial power distribution on dryout: Film-flow models and experiments C Adamsson, H Anglart Nuclear Engineering and Design 240 (6), 1495-1505, 2010 | 42 | 2010 |
| Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies C Adamsson, JM Le Corre Nuclear engineering and design 241 (8), 2843-2858, 2011 | 38 | 2011 |
| Film flow measurements for high-pressure diabatic annular flow in tubes with various axial power distributions C Adamsson, H Anglart Nuclear engineering and design 236 (23), 2485-2493, 2006 | 37 | 2006 |
| An assessment of entrainment correlations for the dryout prediction in BWR fuel bundles F Secondi, C Adamsson, JM Le Corre | 18 | 2009 |
| Transient dryout prediction using a computationally efficient method for sub-channel film-flow analysis C Adamsson, JM Le Corre Nuclear Engineering and Design 280, 316-325, 2014 | 16 | 2014 |
| Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser D Papini, C Adamsson, M Andreani, HM Prasser Nuclear Engineering and Design 278, 542-557, 2014 | 11 | 2014 |
| The MONA subchannel analysis code-part A: model description M Nordsveen, N Hoyer, C Adamsson, H Anglart | 11 | 2003 |
| Validation of VIPRE-W sub-channel void predictions using NUPEC/BFBT measurements K Brynjell-Rahkola, JM Le Corre, C Adamsson | 9 | 2009 |
| MEFISTO: a mechanistic tool for the prediction of critical power in BWR fuel assemblies C Adamsson, JM Le Corre International Conference on Nuclear Engineering 48167, 735-747, 2008 | 8 | 2008 |
| Experimental investigation of the liquid film for annular flow in a tube with various axial power distributions C Adamsson, H Anglart, P Persson, S Hedberg | 7 | 2005 |
| Dryout and power distribution effects in boiling water reactors C Adamsson KTH, 2009 | 6 | 2009 |
| A model for inertial drop deposition suitable to predict obstacle effect D Caraghiaur, C Adamsson, H Anglart Nuclear Engineering and Design 260, 121-133, 2013 | 5 | 2013 |
| Study of condensation heat transfer in passive safety systems using GOTHIC and TRACE codes D Papini, C Adamsson, M Andreani, HM Prasser Proc. 9th Int. Topical Meeting on Nuclear Thermal-Hydraulics, Operation and …, 2012 | 5 | 2012 |
| Dryout predictions in BWR fuel assemblies with spacers C Adamsson, H Anglart | 5 | 2004 |
| Modeling of dryout in channels with various spatial power distributions H Anglart, C Adamsson | 5 | 2003 |
| Simulation of International Standard Problem ISP-42, Phase B, using in-house coupled code GOTHIC-TRACE C Adamsson, D Papini, O Zerkak, HM Prasser The 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics …, 2013 | 4 | 2013 |
| Development of a model for prediction of annular flow and dryout in BWR fuel assemblies with spacers M Krejci, C Adamsson, H Anglart NURETH-11, 2005 | 4 | 2005 |
| Deposition of Inertial Drops in Eulerian Formulation D Caraghiaur, C Adamsson, H Anglart NURETH-15 15th International Topical Meeting on Nuclear Reactor …, 2013 | 3 | 2013 |
| Transient void, pressure drop and critical power BFBT Benchmark analysis and results with VIPRE-W/MEFISTO-T JM Le Corre, C Adamsson, P Alvarez | 3 | 2011 |
