Παρακολούθηση
Victor Hugo Sanchez-Espinoza
Victor Hugo Sanchez-Espinoza
Karlsruhe Institute of Technology (KIT), Institute of Neutron Physics and Reactor Technolgoy (INR)
Η διεύθυνση ηλεκτρονικού ταχυδρομείου έχει επαληθευτεί στον τομέα kit.edu - Αρχική σελίδα
Τίτλος
Παρατίθεται από
Παρατίθεται από
Έτος
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
1162012
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
842015
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
812015
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
622015
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
542013
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
472012
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
472009
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
462021
SUBCHANFLOW: a thermal hydraulic sub-channel program to analyse fuel rod bundles and reactor cores
V Sanchez, U Imke, A Ivanov, R Gomez
462010
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
442011
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
432020
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
402020
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
382019
SUBCHANFLOW. A new empirical knowledge based subchannel code
U Imke, V Sanchez, R Gomez
Annual meeting on nuclear technology 2010. Documentation, 2010
382010
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
362011
A flexible coupling scheme for Monte Carlo and thermal-hydraulics codes
JE Hoogenboom, A Ivanov, V Sanchez, C Diop
International Conference on Mathematics and Computational Methods Applied to …, 2011
352011
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
342020
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
312014
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
292011
Investigations of the VVER-1000 coolant transient benchmark phase 1 with the coupled system code RELAP5/PARCS
S Espinoza, V Hugo, M Böttcher
Progress in Nuclear Energy 48 (8), 865-879, 2006
292006
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