Validation of the subchannel code SUBCHANFLOW using the NUPEC PWR tests (PSBT) U Imke, VH Sanchez Science and Technology of Nuclear Installations 2012 (1), 465059, 2012 | 98 | 2012 |
High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW M Daeubler, A Ivanov, BL Sjenitzer, V Sanchez, R Stieglitz, ... Annals of Nuclear Energy 83, 352-375, 2015 | 81 | 2015 |
Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project B Chanaron, C Ahnert, N Crouzet, V Sanchez, N Kolev, O Marchand, ... Annals of Nuclear Energy 84, 166-177, 2015 | 73 | 2015 |
Coupling of dynamic Monte Carlo with thermal-hydraulic feedback BL Sjenitzer, JE Hoogenboom, JJ Escalante, VS Espinoza Annals of Nuclear Energy 76, 27-39, 2015 | 60 | 2015 |
High fidelity simulation of conventional and innovative LWR with the coupled Monte-Carlo thermal-hydraulic system MCNP-SUBCHANFLOW A Ivanov, V Sanchez, R Stieglitz, K Ivanov Nuclear engineering and design 262, 264-275, 2013 | 54 | 2013 |
Development of a coupling scheme between MCNP and COBRA-TF for the prediction of the pin power of a PWR fuel assembly V Sanchez, A Al-Hamry | 47 | 2009 |
DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters–Part I: Development, implementation and verification AM Gomez-Torres, VH Sanchez-Espinoza, K Ivanov, R Macian-Juan Annals of nuclear energy 48, 108-122, 2012 | 46 | 2012 |
Development of a coupling scheme between MCNP5 and SUBCHANFLOW for the pin-and fuel assembly-wise simulation of LWR and innovative reactors A Ivanov, V Sanchez, U Imke | 44 | 2011 |
SUBCHANFLOW: a thermal hydraulic sub-channel program to analyse fuel rod bundles and reactor cores V Sanchez, U Imke, A Ivanov, R Gomez | 44 | 2010 |
The EC MUSA project on management and uncertainty of severe accidents: main pillars and status LE Herranz, S Beck, VH Sánchez-Espinoza, F Mascari, S Brumm, ... Energies 14 (15), 4473, 2021 | 36 | 2021 |
Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore D Ferraro, M García, V Valtavirta, U Imke, R Tuominen, J Leppänen, ... Annals of Nuclear Energy 137, 107090, 2020 | 36 | 2020 |
SUBCHANFLOW. A new empirical knowledge based subchannel code U Imke, V Sanchez, R Gomez Annual meeting on nuclear technology 2010. Documentation, 2010 | 36 | 2010 |
Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests D Ferraro, M García, V Valtavirta, U Imke, R Tuominen, J Leppänen, ... Annals of Nuclear Energy 142, 107387, 2020 | 34 | 2020 |
Review and proposal for heat transfer predictions at supercritical water conditions using existing correlations and experiments W Jäger, VHS Espinoza, A Hurtado Nuclear engineering and design 241 (6), 2184-2203, 2011 | 34 | 2011 |
A flexible coupling scheme for Monte Carlo and thermal-hydraulics codes JE Hoogenboom, A Ivanov, V Sanchez, C Diop | 34 | 2011 |
Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes–PREMIUM benchmark T Skorek, A de Crécy, A Kovtonyuk, A Petruzzi, R Mendizábal, ... Nuclear Engineering and Design 354, 110199, 2019 | 30 | 2019 |
Internal multi-scale multi-physics coupled system for high fidelity simulation of light water reactors A Ivanov, V Sanchez, R Stieglitz, K Ivanov Annals of Nuclear Energy 66, 104-112, 2014 | 30 | 2014 |
Development of multi-physics code systems based on the reactor dynamics code DYN3D S Kliem, A Gommlich, A Grahn, U Rohde, J Schuetze, T Frank, A Gomez, ... Kerntechnik 76 (3), 160-165, 2011 | 29 | 2011 |
A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors M García, R Tuominen, A Gommlich, D Ferraro, V Valtavirta, U Imke, ... Annals of Nuclear Energy 139, 107213, 2020 | 28 | 2020 |
Validation of the Serpent 2-DYNSUB code sequence using the special power excursion reactor test III (SPERT III) M Knebel, L Mercatali, V Sanchez, R Stieglitz, R Macian-Juan Annals of Nuclear Energy 91, 79-91, 2016 | 28 | 2016 |