Portal de Transparencia

Actividad investigadora:

• Artículos en revistas
  • [2018] A comparison of uncertainty propagation techniques using NDaST: full, half or zero Monte Carlo
  • [2018] CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen
  • [2018] Checking, processing and verification of nuclear data covariances
  • [2015] Comparison of nuclear data uncertainty propagation methodologies for PWR burn-up simulations
  • [2015] Inventory calculation and nuclear data uncertainty propagation on light water reactor fuel using ALEPH-2 and SCALE 6.2
  • [2015] Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in One-group or Multi-group
  • [2014] Analysis of 238 Pu and 56 Fe Evaluated Data for Use in MYRRHA
  • [2014] Analysis of Pu-238 and Fe-56 Evaluated Data for Use in MYRRHA
  • [2014] Educating Nuclear Engineers by Nuclear Science and TEchnology Master at UPM
  • [2014] Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and their Irradiated Fuel - a Comparison between Libraries
  • [2014] Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and their Irradiated Fuel - a Comparison between Libraries
  • [2014] Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
  • [2014] Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
  • [2014] Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
  • [2014] PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
  • [2014] PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
  • [2014] PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
  • [2014] Processing and Validation of JEFF-3.1.2 Cross-section Library into Various Formats: ACE, PENDF, GENDF, MATXSR and BOXER
  • [2014] Propagation of Neutron Cross Section, Fission Yield, and Decay Data Uncertainties in Depletion Calculations
  • [2014] Propagation of Nuclear Data Uncertainties for PWR core Analysis
  • [2014] Testing JEFF-3.1.1 and ENDF/B-VII.1 Decay and Fission Yield Nuclear Data Libraries with Fission Pulse Neutron Emission and Decay Heat Experiments
  • [2014] Testing JEFF-3.1.1 and ENDF/B-VII.1 Decay and Fission Yield Nuclear Data Libraries with Fission Pulse Neutron Emission and Decay Heat Experiments
  • [2014] The Activities of the European Consortium on Nuclear Data Development and Analysis for Fusion
  • [2013] Methodologies for an improved prediction of the isotopic content in high burnup samples. Application to Vandellos-II reactor core
  • [2013] Methodologies for an improved prediction of the isotopic content in high burnup samples. Application to Vandellos-II reactor core
  • [2013] Monte Carlo uncertainty propagation approaches in ADS burn-up calculations
  • [2013] Monte Carlo uncertainty propagation approaches in ADS burn-up calculations
  • [2013] Presentation and Discussion of the UAM/Exercise I-1b: "Pin-Cell Burn-Up Benchmark" with the Hybrid Method
  • [2013] Presentation and Discussion of the UAM/Exercise I-1b: ?Pin-Cell Burn-Up Benchmark? with the Hybrid Method
  • [2013] Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1
  • [2013] Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1
  • [2013] Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1
  • [2013] Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1
  • [2013] Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1
  • [2013] Uncertainty Analysis in Reactor Physics Modeling
  • [2012] Analysis of Different Uncertainty Activation Cross Section Data Libraries for LWR, ADS and DEMO Neutron Spectra
  • [2012] Importance of Nuclear Data Uncertainties in Criticality Calculations
  • [2011] Desarrollo de códigos neutrónicos propios para la simulación del núcleo de reactores PWR
  • [2011] Education and training of future nuclear engineers throught the use of an interactive plant simulator
  • [2011] Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
  • [2011] Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
  • [2011] Impact of nuclear data uncertainties in the Phase-1B Benchmark
  • [2011] Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
  • [2011] Study on the response of IFMIF fission chambers to mixed neutron-gamma fields: PH-2 experimental tests
  • [2010] Assessment of fissionable material behaviour in fission chambers
  • [2010] Assessment of fissionable material behaviour in fission chambers
  • [2010] Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
  • [2010] Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
  • [2010] Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
  • [2009] Effect of activation cross section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
  • [2009] Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
  • [2009] Feasibility of fission chambers as a neutron diagnostic in the IFMIF Test Cell
  • [2009] Feasibility of fission chambers as a neutron diagnostic in the IFMIF-Test Cell
  • [2008] 3D neutronic calculations: CAD-MCNP methodology applied to vessel activation in KOYO-F
  • [2008] Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE structural materials
  • [2008] Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations
  • [2007] Applications of Monte Carlo techniques for propagation of cross section uncertainties to actinide inventory in ADS transmuters: comparison with sensitivity analysis
  • [2007] Assessment of uncertainties in the prediction of actinide inventory in accelerator-driven transmutation dedicated systems
  • [2007] Transmutations analysis of realistic low-activation steels for magnetic fusion reactors and IFMIF
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• Capítulos de libros
  • [2016] Results of UPM and CSN for the Burn-up Credit Criticality Safety Benchmark Phase III-C
  • [2008] 3D neutronic calculations: CAD-MCNP methodology applied to vessel activation in KOYO-F
  • [2008] Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE structural materials
  • [2007] Advances in materials physics for IFE at DENIM
  • [2007] Advances in target design and materials physics for IFE at DENIM
  • [2007] Comparison of Monte Carlo neutron transport codes and Nuclear Data libraries for neutron calculations in different IFE concepts
  • [2007] Impact of activation cross section uncertainties on the waste management performance of irradiated steels under different neutron environments of IFE Thick-Liquid concepts
  • [2007] Safety and environmental analysis for fusion facilities: Methodologies and Applications
  • [2007] Safety and environmental considerations for laser IFE chambers
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• Conferencias invitadas en congresos
  • [2011] Impact of Nuclear Data Uncertainties in the Phase-1B Benchmark
  • [2009] EFF/EAF Meeting NEA
  • [2009] IAEA Technical Meeting in colaboration with NEA on Specific Applications of Research Reactor: Provision of Nuclear Data.
• Cursos, seminarios y tutoriales
  • [2019] The importance of nuclear data for nuclear applications and the JEFF Project' (A.Plompen, JRC/EU)
  • [2018] Example of a Bayesian Monte Carlo (BMC) Technique applied for 235U adjustment using Criticality and Transmission Integral Benchmarks
  • [2018] JEFF Processing, Verification, Benchmarking and Validation Meeting: Introduction.
  • [2018] On the International Radiation Characterization Benchmarks Experiment Project (IRCBEP): User s Point of View
  • [2018] Recent Updates to the Nuclear Data Sensitivity Tool (NDaST),
  • [2018] Upgraded SEANAP-PWR core simulator with JEFF-3.3: Impact of Nuclear Data Uncertainties for PWR Cycle Operation
  • [2018] WPNCS-SG3 Benchmark on the effect of temperature on the keff for PWR fuel assemblies and Computational Benchmark for the Doppler Reactivity Defect,
  • [2012] Calculations of Fission Pulse Neutron Emission: A comparison between JEFF-3.1.1. and ENDF/B-VII.1
  • [2012] IMPORTANCE OF NUCLEAR DATA UNCERTAINTIES IN CRITICALITY AND BURNUP CALCULATIONS FOR LWR
  • [2012] Presentation and discussion of submitted results for Exercise 1b: ?Pin cell burnup benchmark
  • [2012] Processing of the JEFF-3.1.2 Cross Section Library into various formats (ACE, PENDF, GENDF, MATXSR and BOXER) for testing purposes
  • [2012] TASK 2.4 Covariances for activation, radioactive decay and fission yields
  • [2012] UPM Activities on the STLs processing (Task 6.2 ) and the generation of DPA cross section library up to 150 MeV (Task 4.1)
  • [2010] Lesson 1. Improvements in the prediction capability of activation codes: Error propagation of nuclear data uncertainty. Examples
  • [2010] Lesson 2. Nuclear data requirements for ADS: Uncertainty and sensitivity study
  • [2010] Lesson 3. Exercises with ACAB code. Examples¿
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• Libros
  • [2007] 29th International Conference on Laser Interaction with Matter
• Otras Publicaciones
  • [2019] A comparison of ENDF/B-VIII.0 to some other evaluations for different criticality calculations in thermal systems.
  • [2019] P&V of JEFF-3.3 by Using FRENDY Code
  • [2019] Resumen de las Jornadas de Usuarios de Datos Nucleares y JEFF Stakeholders meeting T
  • [2019] UPM contribution to WPEC/SG47
  • [2019] Actividades de la OECD/NEA
  • [2019] Actividades de la OECD/NEA,
  • [2019] Comparison of JEFF-3.3 and ENDF/B-VIII.0 in PWR simulations
  • [2019] Current activities on Processing and Verification (P&V) at Universidad Politécnica de Madrid
  • [2019] Experiencia de datos nucleares en simulaciones PWR
  • [2019] First feedback on using FRENDY for processing of JEFF-3.3
  • [2019] OECD/NEA WPEC SG 46: ''Joint CIEMAT and UPM contribution: ASTRID, ALFRED and MYRRHA''
  • [2019] OECD/NEA WPEC SG 46: ''Status on MYRRHA, ESFR, ASTRID and ALFRED''
  • [2019] Organización por la OECD/NEA del JEFF Stakeholders Meeting
  • [2019] Resumen de Actividades y propuesta de nuevas por la UPM.
  • [2019] Status on MYRRHA, ESFR, ASTRID and ALFRED
  • [2019] UPM contribution to ACTION 6: 'Revision of TAR tables'
  • [2019] UPM/IAEA contributions to inter-comparison study
  • [2019] WPEC/SG40: An Extended Summary of the Collaborative International Evaluated Library Organisation (CIELO) Pilot Project.7498,
  • [2013] Accurate Nuclear Data for nuclear Energy Sustainability
  • [2013] Accurate Nuclear Data for nuclear Energy Sustainability
  • [2008] International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" (PHYSOR 08)
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• Otros méritos
  • [2009] Activación, transmutación y cálculo de dosis en materiales irradiados con protones
  • [2009] Análisis de sensibilidad e incertidumbre del Benchmark de Burnup Credit Phase-VII de la NEA/OECD
  • [2009] Cálculos de activación y transmutación en materiales irradiados con partículas cargadas
  • [2009] Estudio de la metodología de propagación de incertidumbre de datos nucleares en cálculos de transporte de radiación mediante códigos deterministas: Aplicación en cálculos de blindaje
  • [2009] Estudio del comportamiento del material fisionable en cámaras de fisión para distintos escenarios neutrónicos
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• Ponencia en Congresos
  • [2019] CDIO Course Development for Design and Simulation of PWRs
  • [2019] Comparison of JEFF-3.3 and ENDF/B-VIII.0 Nuclear Data Libraries in PWR Simulations
  • [2019] Use of Shielding Integral Benchmark Archive and Database for Nuclear Data Validation
  • [2018] Examples of Monte Carlo Techniques Applied for Nuclear Data Uncertainty Propagation, WONDER2018
  • [2017] Neutron-induced nuclear data for the MYRRHA fast spectrum facility
  • [2017] Neutron-induced nuclear data for the MYRRHA fast spectrum facility
  • [2017] Neutron-induced nuclear data for the MYRRHA fast spectrum facility
  • [2017] Neutron-induced nuclear data for the MYRRHA fast spectrum facility
  • [2016] Nuclear data sensitivity analysis and evaluated data library comparison for MYRRHA relevant quantities
  • [2014] IMPACT OF THE FISSION YIELD NUCLEAR DATA UNCERTAINTIES IN THE PIN-CELL BURN-UP OECD/NEA UAM BENCHMARK
  • [2014] Impact of the Fission Yield Covariance Data in Burn-up Calculations (JEF/DOC-1566)
  • [2014] Nuclear Data Uncertainty Propagation in Depletion Calculations of Advanced Reactor Systems with Comparison of Using One-group or Multigroup Cross-Sections
  • [2014] Processing of the new JEFF-3.2T4 Cross Section Library with the NJOY Code System into Various Formats for Testing Purposes
  • [2014] Propagation of U-235. U-238, Pu-239 and H in H2O nuclear data uncertainties for PWR core analysis
  • [2014] SENSITIVITY/UNCERTAINTY ANALYSIS FOR BWR CONFIGURA-TIONS OF EXERCISE I-2 OF UAM BENCHMARK
  • [2014] Student oportunities in the frame of the European Project GENTLE
  • [2013] Analysis of Neutron Thermal Scattering Data Uncertainties in PWRs
  • [2013] Analysis of the Quality of Evaluated Data for Most Relevant Reactions of MYRRHA
  • [2013] Application of a Bayesian/Generalised Least-Squares method to generate correlations between independent neutron fission yield data
  • [2013] GRS Results for the Burnup Pin-cell Benchmark Propagation of Cross-Section, Fission Yields and Decay Data Uncertainties
  • [2013] Generation of Fission Yield covariance data and application to Fission Pulse Decay Heat calculations (JEF/DOC-1520)
  • [2013] Generation of a complete damage energy cross-section library up to 150 MeV based on JEFF -3.1.1
  • [2013] Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and Their Irradiated Fuel. Comparison between Libraries
  • [2013] Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor Tipo de participación: Publicación: Para su publicación enLugar celebración: NY (USA) Fecha: March 4-8, 2013
  • [2013] Preparing Exercise I-3: Optimization of cross-section tables using sensitivity coefficients in COBAYA3 Congreso:Fecha y lugar de celebración: París, Francia. Abril 10-12, 2013
  • [2013] Processing and generation of DPA cross section library up to 150 MeV (EFFDOC-1203)
  • [2013] Processing and validation of JEFF3.1.2 cross-section library into various formats: ACE, PENDF, GENDF, MATXSR and BOXER
  • [2013] Processing of a Damage Energy Cross-Section Library Based on JEFF3.1.1/2 & the Potential Impact of Nuclear Data Uncertainties on Damage Energy and Gas Production Cross-Sections
  • [2013] Processing of the JEFF-3.2T3 Cross Section Library with the NJOY Code System into Various Formats for Testing Purposes
  • [2013] Progress on Spent Fuel Data Compilations at UPM Octubre 8-9, 2013
  • [2013] Propagation of Neutron Cross Section, Fission Yield, and Decay Data Uncertainties in Depletion Calculations
  • [2013] Propagation of U235-238, Pu239 and STL Nuclear Data Uncertainties for PWR core analysis (JEF/DOC-1524)
  • [2013] Testing JEFF-3.1.1 and ENDF/B-VII.1 Decay and Fission Yield Nuclear Data Libraries with Fission Pulse Neutron Emission and Decay Heat Experiments
  • [2013] The Nuclear Science and Technology master at the Universidad Politecnica de Madrid
  • [2013] Thermal Scattering Libraries Processing (F4E, Task 6.2)
  • [2013] Towards a complete propagation of nuclear data uncertainties Fission yields and decay data
  • [2013] UPM Activities on Sensitivity and Uncertainty Analysis of Assembly Depletion Abril 10-12, 2013
  • [2013] UPM Activities on the generation of DPA cross section library up to 150 MeV (Task 4.1)
  • [2013] UPM activities on: Nuclear Data (processing), Activation-Source Term Calculation and Uncertainty Propagation
  • [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
  • [2012] Processing of the JEFF-3.1.2 Cross Section Library into various formats (ACE, PENDF, GENDF, MATXSR and BOXER) for testing purposes
  • [2012] UPM Activities on the STLs processing (Task 6.2 ) and the generation of DPA cross section library up to 150 MeV (Task 4.1)
  • [2011] A Comparison of Sensitivity/Uncertainty Methodologies for the Tritium Production in the HFTM/IFMIF Specimen Cells and measurements in Tritium activity in HCLL TBM mock-up LiPb
  • [2011] A Comparison of different Uncertainty Activation Cross-Section Data Libraries and collapsed values for different neutron spectra: ADS, FISSION and FUSION
  • [2011] A Comparison of diffferent Uncertainty Activation Cross-Section Data Libraries: Application to the Prediction Uncertainty in Tritium Production
  • [2011] Analysis of different uncertainty activation cross section data libraries for LWR, ads and demo neutron spectra
  • [2011] Burnup Uncertainty Analysis for PWR-HFP Exercise I-1
  • [2011] Formación y entrenamiento de ingenieros nucleares mediante el máster de Ciencia y Tecnología nuclear de la UPM
  • [2011] Importance of Nuclear Data Uncertainties in Criticality Calculations
  • [2011] Isotopic prediction calculation methodologies: application to Vandellos-II Reactor cycles 7-11
  • [2011] Isotopic prediction simulations applied to high burnup samples irradiated in VANDELLÓS-II Reactor core
  • [2011] Isotopic uncertainty assessment due to nuclear data uncertainties in high-burnup samples
  • [2011] Propagation of nuclear data uncertainties in fuel cycle calculations using MONTE-CARLO Technique
  • [2011] UPM Results BWR-PWR Exercise I-1 by MCNP5 code
  • [2011] Uncertainty assessment methodologies applied to Tritium production in fusion lithium breeding blankets
  • [2011] Uncertainty methods inactivation and inventory calculations
  • [2011] Updated Co-58 evaluation for background capture reaction (MT102) (JEF/DOC-1367)
  • [2010] Assessment of fissionable material behaviour in fission chambers
  • [2010] EDUCATION AND TRAINING OF FUTURE NUCLEAR ENGINEERS THROUGH THE USE OF AN INTERACTIVE PLANT SIMULATOR
  • [2010] Education and Training of Future Nuclear Engineers at DIN: From Advanced Computer Codes to an Interactive Plant Simulator
  • [2010] Keff Sensitivity/Uncertainty Analysis of the Phase VII Burnup Credit Benchmark
  • [2010] Neutron Cross-Section Covariances: Users' perspectives
  • [2010] PROPAGATION OF NUCLEAR DATA UNCERTAINTIES IN TRANSMUTATION CALCULATIONS USING ACAB CODE
  • [2009] Impact of activation cross section uncertainties on the tritium production in the HFTM specimen cells
  • [2009] Impact of activation cross section uncertainties on the tritium production in the HFTM specimen cells
  • [2009] Improvements in the Prediction Capability of ACAB Code to Transmutation Analysis in IFMIF
  • [2009] Improvements in the Prediction Capability of Codes Used to Design Innovative Reactors
  • [2008] Feasibility of a neutron diagnostic for the IFMIF test cell
  • [2008] Impact of different correlation structures in cross-section covariance matrices on the inventory and inventory-related parameters
  • [2008] Progress in Inertial Fusion and Fusion Technology at DENIM
  • [2008] Target Physics and Materials for Inertial Fusion and Fusion Technology at DENIM
  • [2007] 3D Neutronic Calculations: CAD-MCNP Methodology applied to Vessel Activation in KOYO-F
  • [2007] Application of Monte Carlo Techniques for Propagation of Cross Section Uncertainties to Actinide Inventory in ADS Transmuters: Comparison with Sensitivity Analysis
  • [2007] Assessment of Uncertainties in the Prediction of Actinide Inventory in Accelerator-Driven Transmutation Dedicated Systems
  • [2007] Cámaras de fisión miniaturizadas para medidas neutrónicas en IFMIF
  • [2007] Effect of Activation Cross Section Uncertainties in Transmutation Analysis of Realistic Low-Activation Steels for IFMIF
  • [2007] Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
  • [2007] Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
  • [2007] Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE structural materials
  • [2007] Processing and validation of JEFF3.1 library in ACE format at 10 different temperatures
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• Proyectos de I+D+i
  • [2018] CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
  • [2017] ESFR-SMART: European Sodium Fast Reactor Safety Measures Assessment and Research Tools
  • [2014] COLABORACIÓN EN EL ÁREA DE SIMULACIÓN CON CÓDIGOS NEUTRONICOS
  • [2013] CHANDA (Solving Challenge in Nuclear Data)
  • [2013] CHANDA: solving CHAllenges in Nuclear DAta
  • [2013] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2013] COLABORACIÓN EN EL ÁREA DE SIMULACIÓN CON CÓDIGOS NEUTRONICOS
  • [2013] ESNII plus: Preparing ESNII for HORIZON 2020
  • [2013] GENTLE: Graduate and Executive Nuclear Training and Lifelong Education
  • [2013] NURESAFE: NUCLEAR REACTOR SAFETY SIMULATION PLATFORM
  • [2013] ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
  • [2012] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2012] F4E-GRT-168.01: Nuclear Data Improvements and Development of Tools-Nuclear data Evaluation
  • [2012] F4E-GRT-168.01: Nuclear Data Improvements and Development of Tools-Nuclear data Evaluation
  • [2012] NUCLEAR DATA IMPROVEMENTS AND DEVELOPMENT OF TOOLS-NUCLEAR DATA EVALUATION
  • [2012] ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
  • [2011] COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
  • [2011] ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
  • [2010] ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRITICIDAD
  • [2009] CREDITO AL QUEMADO EN LOS ANALISIS DE SEGURIDAD FRENTE A CRITICIDAD
  • [2009] Convenio CIEMAT/DENIM en el marco del Programa de Actividades de Seguimiento (keep-in-touch) de la Fusión Nuclear por Confinamiento Inercial (IFE) para la producción de energía de la Unión Europea. (ref.: 08/061)
  • [2008] Support for the procesing of Cross Section Libraries
  • [2007] Cooperación en el campo de la fusión nuclear por confinamiento inercial y tecnologia de la fusión
  • [2007] Fusión por impacto y materiales y sistemas bajo irradiación en experimentos y demostradores de fusión nuclear II
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• Registros de Software
  • [2014] Thermal Scattering Libraries processed to ACE format. NEA-1883 ZZ-TSL-ACE/2013
  • [2014] Thermal Scattering Libraries processed to ACE format. RSICC DATA LIBRARY DLC-270.
• Responsabilidades
  • [2019] 'OECD/NEA/JEFF/P&V-B&V - Nov.2019' - Processing, Verification, Benchmarking and Validation
  • [2019] DESARROLLO DEL ACOPLAMIENTO ENTRE SERPENT 2 Y ANSYS CFX PARA EL REACTOR DE INVESTIGACIÓN FRM II
  • [2019] Co-Chair organizador de I Jornada CEIDEN de usuarios de bases de datos nucleares utilizadas en cálculos para aplicaciones nucleares energéticas y no-energéticas :
  • [2019] Introduction into the field of nuclear data evaluation Conferencia impartida por H.Leeb, TUW/Austria
  • [2019] Introduction to IAEA Nuclear Data Service and EXFOR Conferencia impartida por N.Otsuka, IAEA/NDS
  • [2019] The importance of nuclear data for nuclear applications and the JEFF Project' Conferencia impartida por A.Plompen, JRC/EU
  • [2018] Monitor del WPEC SG47 "Use of Shielding Integral Benchmark Archive and Database for Nuclear Data Validation", (2018-). WPEC (Working Party on International Nuclear Data Evaluation Co-operation).
  • [2018] Representante Español en el Nuclear Science Committee (NSC) de la OECD/NEA
  • [2014] 7FP GENTLE intersemester course on nuclear data
  • [2013] ?Recent developments in ORIGEN code. Application for the extension of burnup credit in the U.S.A.?, Ian Gauld, ORNL/USA
  • [2013] Desarrollo de una metodología para implementar WIMSD5 en el sistema SEANAP
  • [2013] Miembro del grupo internacional de desarrollo de la librería TENDL2013
  • [2013] Procesamiento de Librerías de Dispersión Térmica de neutrones y estudio del impacto de sus incertidumbres en cálculos de reactores de agua a presión
  • [2012] ANÁLISIS TERMO-HIDRÁULICO DE SUB-CANALES DE UN ELEMENTO BWR CON EL CÓDIGO COBRA-TF
  • [2012] Delayed neutrons evaluations with JEFF-3.1.1 and ENDF/B-VII.1 data libraries
  • [2012] ESTUDIO DE LIBRERÍAS EVALUADAS FOTONUCLEARES Y PROCESAMIENTO PARA MCNP
  • [2012] Estudio del comportamiento termomecánico del combustible nuclear de reactores LWR mediante códigos de cálculo tipo FEMAXI?VI
  • [2012] Metodología de acoplamiento para cálculos de quemado del combustible GE14-BWR
  • [2012] Organización 2012 Serpent International Users Group Meeting
  • [2011] Director del Proyecto Fin de Carrera: Propagación de incertidumbres de los cálculos neutrónicos en una celda de combustible para reactores LWR
  • [2011] Director del Proyecto Fin de Master: Metodologías de cálculo de predicción isotópica sistema link/[MONTEBURNS 2.0], aplicado a combustible irradiado en Vandellós-II¿
  • [2011] Director del Proyecto Fin de Master: Propagación de incertidumbre de datos nucleares en cálculos de ciclos de combustible mediante técnica de Monte Carlo
  • [2011] Director del Proyecto Fin de Master: Propagación de incertidumbres en cálculos neutrónicos con MCNP: Participación en el Ejercicio I-1 del Benchmark de UAM para LWR
  • [2010] Actualización de la metodología de cálculo MCNP+ACAB con los nuevos desarrollos implementados en el código Monteburns 2.0
  • [2010] Estudio de la metodología para la predicción del inventario isotópico en el combustible PWR
  • [2010] Estudio de la propagación de las incertidumbres de los datos nucleares en cálculos de transmutación
  • [2010] Task 2.4 Covariances for activation, radioactive decay and fission yields
  • [2010] WP2: Uncertainties and covariances of nuclear data
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• Tesis Doctorales
  • [2016] FISSION CHAMBERS DESIGNER BASED ON MONTE CARLO TECHNIQUES WORKING IN CURRENT MODE AND OPERATED IN SATURATION REGIME
  • [2014] Development of a Methodology for Nuclear Data Uncertainty Propagation on Isotopic Evolution Calculations for Advanced Nuclear Systems