| Uncertainty and sensitivity of neutron kinetic parameters in the dynamic response of a PWR rod ejection accident coupled simulation C Mesado, A Soler, T Barrachina, R Miró, JC García-Díaz, R Macián-Juan, ... Science and Technology of Nuclear Installations 2012, 2012 | 10 | 2012 |
| Two dimesnional modelling with CFD of the behavior of a ventilated ceramic façade C Mesado, S Chiva, E Juliá, L Hernández 5th European Conference on Computational Fluid Dynamics, ECCOMAS CFD, 2010 | 9 | 2010 |
| Uncertainty Quantification and Sensitivity Analysis for Cross Sections and Thermohydraulic Parameters in Lattice and Core Physics Codes. Methodology for Cross Section Library … C Mesado Melia Universitat Politècnica de València, 2017 | 7 | 2017 |
| Validation of 3D neutronic-thermalhydraulic coupled codes RELAP5/PARCSv2. 7 and TRACEv5. 0P3/PARCSv3. 0 against a PWR control rod drop transient M Garcia-Fenoll, C Mesado, T Barrachina, R Miró, G Verdú, JA Bermejo, ... Journal of Nuclear Science and Technology 54 (8), 908-919, 2017 | 5 | 2017 |
| Comparison of depletion results for a boiling water reactor fuel element with CASMO and SCALE 6.1 (TRITON/NEWT) C Mesado, D Morera, R Miro, T Barrachina, G Verdú, A Concejal, A Soler, ... | 3 | 2013 |
| Cross-Section Generation Using TXT2NTAB Code for Uncertainty Propagation with Burnup Dependence A Labarile, C Mesado, R Miró, G Verdú Nuclear Technology 205 (12), 1675-1684, 2019 | 2 | 2019 |
| Model 3D Cores for PWR Using Vessel Components in TRACEv5. OP3 C Mesado, R Miró, T Barrachina, G Verdú US Nuclear Regulatory Commission, 2016 | 2 | 2016 |
| Control rod drop transient: uncertainty and sensitivity analysis of thermal-hydraulic variables using a 3D model with TRACE V5. 0P3/PARCS 3.0 C Mesado, M Garcia-Fenoll, R Miró, G Verdú 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics …, 2015 | 2 | 2015 |
| Principales Características y Posibilidades del Nuevo Módulo de SCALE 6.2 para Cálculo de Sensibilidad e Incertidumbre por Muestreo: SAMPLER, 40º Reunión Anual Sociedad Nuclear … C Mesado, R Miró, T Barrachina, G Verdú Valencia–España, 2014 | 2 | 2014 |
| Application case for phase III of UAM-LWR benchmark: Uncertainty propagation of thermal-hydraulic macroscopic parameters C Mesado, R Miró, G Verdú Nuclear Engineering and Technology 52 (8), 1626-1637, 2020 | 1 | 2020 |
| TSUNAMI-3D and SAMPLER/KENO comparison for sensitivity and uncertainty analysis in neutron multiplication factor for LWRs A Labarile, T Barrachina, C Mesado, R Miró, G Verdú Proceeding of M&C 2017, 16-20, 2017 | 1 | 2017 |
| Sensitivity and uncertainty analysis in nuclear data with SCALE 6.2 code. Application to LWRs assemblies A Labarile, C Mesado, R Miro, T Barrachina, G Verdu | 1 | 2017 |
| Methodology for neutronic uncertainty propagation and application to a UAM-LWR benchmark C Mesado, R Miró, G Verdú Progress in Nuclear Energy 126, 103389, 2020 | | 2020 |
| Propagación de incertidumbre y sensibilidad en librerías master de secciones eficaces con SCALE 6.2-SAMPLER y DAKOTA C Mesado Melia, R Miró Herrero, TM Barrachina Celda, GJ Verdú Martín Sociedad Nuclear Española, 2015 | | 2015 |
| Main features and possibilities of the new scale module for calculation of sensitivity and uncertainty by sampling: SAMPLER; Principlaes caracteristicas y posibilidades del … C Mesado, R Miro, T Barrachina, G Verdu | | 2014 |
| Comparison of results for burning with BWR reactors CASMO and SCALE 6.2 (TRITON/NEWT); Comparacion de los resultados de quemado para reactores BWR con CASMO y SCALE 6.2 (TRITON … C Mesado, R Miro, T Barrachina, G Verdu | | 2014 |
| Principales características y posibilidades del nuevo módulo de SCALE 6.2 para cálculo de sensibilidad e incertidumbre por muestreo: SAMPLER C Mesado Melia, R Miró Herrero, TM Barrachina Celda, GJ Verdú Martín Grupo Senda, 2014 | | 2014 |
| Comparación de los resultados de quemado para reactores BWR con CASMO y SCALE 6.2 (TRITON/NEWT) C Mesado Melia, R Miró Herrero, TM Barrachina Celda, GJ Verdú Martín, ... Grupo Senda, 2014 | | 2014 |
| Ejecución del modelo Peach Bottom Turbine Trip en estado transitorio con TRACE V5. 0P3/PARCS 3.0 C Mesado Melia, R Miró Herrero, TM Barrachina Celda, GJ Verdú Martín Grupo Senda, 2014 | | 2014 |
| Model with Peach Bottom Turbine trip and thermal-Hydraulic code TRACE V5P3 C Mesado, R Miro, T Barrachina, G Verdu 40 Annual Meeting of Spanish Nuclear Society, Oct 1-3, 2014, Valencia, Spain, 2014 | | 2014 |
Antonella LabarileInvestigadora, Instituto de Seguridad Industrial, Radiofísica y Medioambiental (ISIRYM)Verified email at upv.es
