Observatorio de I+D+i UPM
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RESEARCHERS
RDI STRUCTURES
RESEARCH ACTIVITIES
INNOVATION
Investigador
Diana Cuervo Gomez
Researcher Category
L.D. PRF.CONTR.DOCT.
Role
SUBDIRECTOR DE E.T.S..
UPM Centre
E.T.S. DE INGENIEROS NAVALES
Department:
INGENIERÍA ENERGÉTICA (N)
Knowledge Area
INGENIERIA NUCLEAR
Research Group:
Ciencia y Tecnología de sistemas avanzados de fisión nuclear
Email
d.cuervo
upm.es
Phone
910676225
Research Reports
Proyectos de I+D+i y generación de recursos
29 Proyectos de I+D+i
1: (2007)
European Plataform for Nuclear Reactor Simulations NURESIM
2: (2008)
European Plataform for Nuclear Reactor Simulations NURESIM
3: (2009)
NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
4: (2010)
NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
5: (2011)
NURISP: Nuclear Reactor Integrated Simulation Project
6: (2012)
NUC-MULTPHYS.: Desarrollo de una Plataforma Multifísica de Altas Prestaciones para Simulaciones Termohidráulico-Neutrónicas en Ingeniería Nuclear.
7: (2013)
Desarrollo de una plataforma multifisica de altas prestaciones para simulaciones termohidraulico-neutronicas en ingenieria nuclear
8: (2013)
ESNII plus: Preparing ESNII for HORIZON 2020
9: (2013)
ESNII plus: Preparing ESNII for Horizon 2020
10: (2013)
GENTLE: Graduate and Executive Nuclear Training and Lifelong Education
11: (2013)
GENTLE: Graduate and Executive Nuclear Training and Lifelong Education
12: (2013)
NURESAFE: NUCLEAR REACTOR SAFETY SIMULATION PLATFORM
13: (2013)
NURESAFE: NUCLEAR REACTOR SAFETY SIMULATION PLATFORM Grant Agreement no: 323263
14: (2013)
NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
15: (2014)
ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
16: (2014)
COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
17: (2014)
GRADUATE AND EXECUTIVE NUCLEAR TRAINING AND LIFELONG EDUCATION- GENTLE
18: (2014)
NURESAFE-323263
19: (2014)
NURESAFE-323263
20: (2015)
CÁTEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
21: (2015)
COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
22: (2015)
ISAMAR: Aplicación de la Metodología de Análisis integrado de la seguridad a reactores nucleares avanzados
23: (2015)
Proyecto ISAMAR (Integrated Safety Assessment Methodology Applied to Advanced Reactors)
24: (2016)
CÁTEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
25: (2016)
PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
26: (2017)
European Sodium Fast Reactor Safety Measures Assessment and Research Tools (ESFR-SMART)
27: (2017)
GRADUATE AND EXECUTIVE NUCLEAR TRAINING AND LIFELONG EDUCATION- GENTLE
28: (2017)
PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
29: (2018)
Responsable del Proyecto Propio: Desarrollo de un sistema BEPU para la simulación de reactores PWR
Formación de Investigadores y Movilidad
1 Tesis Doctorales
1: (2010)
Desarrollo e implementación de la descomposición en subdominios del acoplamiento neutrónico-termohidráulico mediante disecciones alternadas con un sistema de cálculo multiescala
Difusión de Resultados de Investigación
26 Artículos en revistas
1: (2008)
Participación española en el desarrollo de la Plataforma Europea para Simulación de Reactores Nucleares (NURESIM)
2: (2009)
A domain decomposition methodology for pin by pin coupled neutronic and thermal-hydraulic analyses in COBAYA3
3: (2010)
A domain decomposition methodology for pin by pin coupled neutronic and thermal-hydraulic analyses in COBAYA3
4: (2011)
Desarrollo de códigos neutrónicos propios para la simulación del núcleo de reactores PWR
5: (2011)
Education and Training of Future Nuclear Engineers Through the use of an Interactive Plant Simulator
6: (2011)
Education and training of future nuclear engineers throught the use of an interactive plant simulator
7: (2012)
Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR
8: (2013)
A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
9: (2013)
A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
10: (2013)
Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmark Databases
11: (2014)
Educating Nuclear Engineers by Nuclear Science and TEchnology Master at UPM
12: (2014)
Effects of cross sections tables generation and optimization on rod ejection transient analyses
13: (2014)
Selected Papers from OECD-NEA PSBT Benchmark
14: (2015)
Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project
15: (2015)
Educational Initiatives to Develop Transversal Skills in the Nuclear Engineering Subjects at Universidad Politecnica de Madrid
16: (2017)
Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
17: (2017)
Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
18: (2017)
Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
19: (2017)
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
20: (2017)
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
21: (2017)
Testing the NURESIM platform on a PWR main steam line break benchmark
22: (2017)
Testing the NURESIM platform on a PWR main steam line break benchmark
23: (2018)
Impact of the homogenization level, nodal or pin-by-pin, on the uncertainty quantification with core simulators
24: (2018)
Impact of the homogenization level, nodal or pin-by-pin, on the uncertainty quantification with core simulators
25: (2018)
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
26: (2018)
Uncertainty quantification: parametric methods assessment
2 Conferencias invitadas en congresos
1: (2017)
Overview of the UPM-CSN activities for Uncertainty Quantification in PWR full core simulations
2: (2017)
Overview of the UPM-CSN activities for Uncertainty Quantification in PWR full core simulations
2 Otras Publicaciones
1: (2008)
Subproject Multi-physics (SP3) Deliverable D3.4 COBAYA3 Integration within the SALOME Platform
2: (2008)
”Integration of ANDES and COBAYA in SALOME”
42 Ponencia en Congresos
1: (2007)
Multiscale and Multiphysics Coupling in COBAYA3
2: (2008)
Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis
3: (2008)
Descomposición espacial en subdominios para reactores de agua ligera a la escala de la barra de combustible
4: (2010)
Aplicación del código COBAYA3 al análisis multiescala con acoplamiento neutrónico-termohidráulico en reactores PWR
5: (2010)
Education and Training of Future Nuclear Engineers at DIN: From Advanced Computer Codes to an Interactive Plant Simulator
6: (2010)
EDUCATION AND TRAINING OF FUTURE NUCLEAR ENGINEERS THROUGH THE USE OF AN INTERACTIVE PLANT SIMULATOR
7: (2010)
Whole Core Pin-by-Pin Coupled Neutronic-Thermal-hydraulic Steady state and Transient Calculations using COBAYA3 code
8: (2011)
ASSESSMENT OF CTF BOILING TRANSITION AND CRITICAL HEAT FLUX MODELING CAPABILITIES USING THE OECD/NRC BFBT AND PSBT BENCHMARK DATABASES
9: (2011)
Formación y entrenamiento de ingenieros nucleares mediante el máster de Ciencia y Tecnología nuclear de la UPM
10: (2011)
Interactive graphic simulation: an advanced methodology to improve the teaching-learning process in nuclear engineering education and training
11: (2011)
Interface discontinuity factors in the modal eigenspace of the multigroup diffusion matrix
12: (2011)
The Key Role Transferring Knowledge Of Nuclear España, The Spanish Nuclear Society Magazine?
13: (2012)
ANÁLISIS DE UN ACCIDENTE SGTR MEDIANTE LA UTILIZACIÓN DEL SIMULADOR GRÁFICO INTERACTIVO DE ZORITA (SGIZ)
14: (2012)
Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project
15: (2012)
Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project
16: (2012)
Initiatives and facilities for E&T in the nuclear science and technology master at UPM
17: (2012)
Initiatives and facilities for E&T in the nuclear science and technology master at UPM
18: (2013)
The Nuclear Science and Technology master at the Universidad Politecnica de Madrid
19: (2013)
UPM activities: Neutronic/Thermohydrulic (COBRA-TF) coupling and Inventory prediction using SCALE6.1 Congreso: Fecha y lugar de celebración: Salamanca, Spain. 19-20 February 2013
20: (2014)
CÁLCULOS DE DIFUSIÓN 3D EN MULTIGRUPOS DE REACTORES LWR MEDIANTE EL USO DE GPU
21: (2014)
DESARROLLO DE UNA HERRAMIENTA DE VERIFICACIÓN PARA CÁLCULOS DE DIFUSIÓN MEDIANTE COBAYA
22: (2014)
Desarrollo de una herramienta de verificación para cálculos de difusión mediante COBAYA
23: (2014)
EFECTOS DE GENERACIÓN Y OPTIMIZACIÓN DE LIBRERÍAS DE SECCIONES EFICACES EN EL ANÁLISIS DE TANSITORIOS EN REACTORES PWR
24: (2014)
Efectos de generación y optimización de librerias de secciones eficaces en ela nalisis de transitorios en reactores PWR
25: (2015)
Acoplamiento de COBAYA4 con la nueva versión de COBRATF
26: (2015)
Acoplamiento independiente y automático entre códigos Neutrónicos y Termohidráulicos
27: (2016)
COMPARISON OF SUBCHANNEL AND AVERAGED CHANNEL THERMAL-HYDRAULIC DESCRIPTIONS ON COUPLED PIN-BY-PIN NEUTRONIC CALCULATIONS
28: (2016)
COMPARISON OF SUBCHANNEL AND AVERAGED CHANNEL THERMAL-HYDRAULIC DESCRIPTIONS ON COUPLED PIN-BY-PIN NEUTRONIC CALCULATIONS
29: (2016)
Efecto de la nodalización neutrónica en el análisis de seguridad de un transitorio MSLB PWR
30: (2016)
Exercise I-3: Comparison of uncertainty propagation in nodal and pin-by-pin calculations using COBAYA code
31: (2016)
Impact of fuel modeling and TH uncertainties in a MSLB scenario
32: (2016)
Preparing uncertainty quantification in multi-physics and multi-scale core simulations using COBAYA and CTF codes
33: (2016)
Thermal-hydraulic uncertainty propagation in a Main Steam Line Break Scenario
34: (2016)
Thermal-hydraulic uncertainty propagation in a Main Steam Line Break Scenario
35: (2017)
Análisis de la incertidumbre en la geometría de la barra combustible y en los modelos mediante la aplicación del sistema DAKOTA/COBRA-TF al ejercicio de la OCDE/NEA Uncertainy Analysis in Best-Estimate Modelling (UAM)
36: (2017)
Análisis de las incertidumbres en los factores de pico de un núcleo PWR
37: (2017)
Análisis de las incertidumbres en los factores de pico de un núcleo PWR
38: (2017)
Coupled calculations COBAYA4/CTF for different MSLB scenarios in the frame of NURESAFE project
39: (2017)
Results for Exercise I-3 with COBAYA: Analysis of the peaking power factors
40: (2017)
Validation of COBAYA4/CTF coupling within European NURESIM Platform against MCNP/CTF
41: (2018)
Neutronic and thermal-hydraulic uncertainty propagation in coupled multiphysics. Neutronic uncertainty effect
42: (2018)
Neutronic and thermal-hydraulic uncertainty propagation in coupled multiphysics. Neutronic uncertainty effect.
• TOMA DE DATOS DE MEMORIAS Y CV
• UPM.ES
S2i 2020 Observatorio de investigación @ UPM con la colaboración del Consejo Social UPM
Cofinanciación del MINECO en el marco del Programa INNPACTO (IPT-020000-2010-22)
