Observatorio de I+D+i UPM
• ESPAÑOL
• ENGLISH
INVESTIGADORES
ESTRUCTURAS DE I+D+I
ACTIVIDAD INVESTIGADORA
INNOVACIÓN
Investigador
Oscar Luis Cabellos De Francisco
Categoría Investigador
CATEDRATICO UNIVERSIDAD
Escuela UPM
E.T.S. DE INGENIEROS INDUSTRIALES
Departamento:
INGENIERÍA ENERGÉTICA
Centros/Institutos I+D+i
INSTITUTO DE FUSION NUCLEAR GUILLERMO VELARDE
Area Conocimiento
INGENIERIA NUCLEAR
Grupo de Investigación:
Fusión Nuclear Inercial y Tecnología de fusión
Email (Directorio UPM)
oscar.cabellos
upm.es
Teléfono (Directorio UPM)
910677121
Datos de Memorias relacionados
Proyectos de I+D+i y generación de recursos
27 Proyectos de I+D+i
1: (2007)
Cooperación en el campo de la fusión nuclear por confinamiento inercial y tecnologia de la fusión
2: (2007)
Fusión por impacto y materiales y sistemas bajo irradiación en experimentos y demostradores de fusión nuclear II
3: (2008)
Support for the procesing of Cross Section Libraries
4: (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)
5: (2009)
CREDITO AL QUEMADO EN LOS ANALISIS DE SEGURIDAD FRENTE A CRITICIDAD
6: (2010)
ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRITICIDAD
7: (2011)
ANDES: Accurate Nuclear Data for nuclear Energy Sustainability
8: (2011)
ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
9: (2011)
COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
10: (2012)
ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
11: (2012)
COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
12: (2012)
F4E-GRT-168.01: Nuclear Data Improvements and Development of Tools-Nuclear data Evaluation
13: (2012)
F4E-GRT-168.01: Nuclear Data Improvements and Development of Tools-Nuclear data Evaluation
14: (2012)
NUCLEAR DATA IMPROVEMENTS AND DEVELOPMENT OF TOOLS-NUCLEAR DATA EVALUATION
15: (2013)
ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
16: (2013)
CHANDA (Solving Challenge in Nuclear Data)
17: (2013)
CHANDA: solving CHAllenges in Nuclear DAta
18: (2013)
COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
19: (2013)
COLABORACIÓN EN EL ÁREA DE SIMULACIÓN CON CÓDIGOS NEUTRONICOS
20: (2013)
ESNII plus: Preparing ESNII for HORIZON 2020
21: (2013)
GENTLE: Graduate and Executive Nuclear Training and Lifelong Education
22: (2013)
GENTLE: Graduate and Executive Nuclear Training and Lifelong Education
23: (2013)
NURESAFE: NUCLEAR REACTOR SAFETY SIMULATION PLATFORM
24: (2014)
COLABORACIÓN EN EL ÁREA DE SIMULACIÓN CON CÓDIGOS NEUTRONICOS
25: (2017)
ESFR-SMART: European Sodium Fast Reactor Safety Measures Assessment and Research Tools
26: (2018)
CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
27: (2019)
SANDA: Supplying Accurate Nuclear Data for energy and non-energy Applications
Formación de Investigadores y Movilidad
2 Tesis Doctorales
1: (2014)
Development of a Methodology for Nuclear Data Uncertainty Propagation on Isotopic Evolution Calculations for Advanced Nuclear Systems
2: (2016)
FISSION CHAMBERS DESIGNER BASED ON MONTE CARLO TECHNIQUES WORKING IN CURRENT MODE AND OPERATED IN SATURATION REGIME
Difusión de Resultados de Investigación
64 Artículos en revistas
1: (2007)
Applications of Monte Carlo techniques for propagation of cross section uncertainties to actinide inventory in ADS transmuters: comparison with sensitivity analysis
2: (2007)
Assessment of uncertainties in the prediction of actinide inventory in accelerator-driven transmutation dedicated systems
3: (2007)
Transmutations analysis of realistic low-activation steels for magnetic fusion reactors and IFMIF
4: (2008)
Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE structural materials
5: (2008)
Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations
6: (2008)
3D neutronic calculations: CAD-MCNP methodology applied to vessel activation in KOYO-F
7: (2009)
Effect of activation cross section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
8: (2009)
Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
9: (2009)
Feasibility of fission chambers as a neutron diagnostic in the IFMIF Test Cell
10: (2009)
Feasibility of fission chambers as a neutron diagnostic in the IFMIF-Test Cell
11: (2010)
Assessment of fissionable material behaviour in fission chambers
12: (2010)
Assessment of fissionable material behaviour in fission chambers
13: (2010)
Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
14: (2010)
Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
15: (2010)
Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
16: (2011)
Desarrollo de códigos neutrónicos propios para la simulación del núcleo de reactores PWR
17: (2011)
Education and Training of Future Nuclear Engineers Through the use of an Interactive Plant Simulator
18: (2011)
Education and training of future nuclear engineers throught the use of an interactive plant simulator
19: (2011)
Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
20: (2011)
Impact of activation cross-section uncertainties on the tritium production in the HFTM specimen cells
21: (2011)
Impact of nuclear data uncertainties in the Phase-1B Benchmark
22: (2011)
Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
23: (2011)
Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
24: (2011)
Study on the response of IFMIF fission chambers to mixed neutron-gamma fields: PH-2 experimental tests
25: (2012)
Analysis of Different Uncertainty Activation Cross Section Data Libraries for LWR, ADS and DEMO Neutron Spectra
26: (2012)
Importance of Nuclear Data Uncertainties in Criticality Calculations
27: (2013)
Methodologies for an improved prediction of the isotopic content in high burnup samples. Application to Vandellos-II reactor core
28: (2013)
Methodologies for an improved prediction of the isotopic content in high burnup samples. Application to Vandellos-II reactor core
29: (2013)
Monte Carlo uncertainty propagation approaches in ADS burn-up calculations
30: (2013)
Monte Carlo uncertainty propagation approaches in ADS burn-up calculations
31: (2013)
Presentation and Discussion of the UAM/Exercise I-1b: "Pin-Cell Burn-Up Benchmark" with the Hybrid Method
32: (2013)
Presentation and Discussion of the UAM/Exercise I-1b: ?Pin-Cell Burn-Up Benchmark? with the Hybrid Method
33: (2013)
Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1
34: (2013)
Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1
35: (2013)
Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1
36: (2013)
Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1
37: (2013)
Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1
38: (2013)
Uncertainty Analysis in Reactor Physics Modeling
39: (2014)
Analysis of Pu-238 and Fe-56 Evaluated Data for Use in MYRRHA
40: (2014)
Analysis of 238 Pu and 56 Fe Evaluated Data for Use in MYRRHA
41: (2014)
Educating Nuclear Engineers by Nuclear Science and TEchnology Master at UPM
42: (2014)
Fission yield covariance generation and uncertainty propagation through fission pulse decay heat calculation
43: (2014)
Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and their Irradiated Fuel - a Comparison between Libraries
44: (2014)
Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and their Irradiated Fuel - a Comparison between Libraries
45: (2014)
Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
46: (2014)
Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
47: (2014)
Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
48: (2014)
Optimization of multidimensional cross-section tables for few-group core calculations
49: (2014)
Processing and Validation of JEFF-3.1.2 Cross-section Library into Various Formats: ACE, PENDF, GENDF, MATXSR and BOXER
50: (2014)
Propagation of Neutron Cross Section, Fission Yield, and Decay Data Uncertainties in Depletion Calculations
51: (2014)
PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
52: (2014)
PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
53: (2014)
PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
54: (2014)
Propagation of Nuclear Data Uncertainties for PWR core Analysis
55: (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
56: (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
57: (2014)
The Activities of the European Consortium on Nuclear Data Development and Analysis for Fusion
58: (2015)
Comparison of nuclear data uncertainty propagation methodologies for PWR burn-up simulations
59: (2015)
Inventory calculation and nuclear data uncertainty propagation on light water reactor fuel using ALEPH-2 and SCALE 6.2
60: (2015)
Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in One-group or Multi-group
61: (2018)
A comparison of uncertainty propagation techniques using NDaST: full, half or zero Monte Carlo
62: (2018)
Checking, processing and verification of nuclear data covariances
63: (2018)
CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen
64: (2019)
Examples of Monte Carlo techniques applied for nuclear data uncertainty propagation
9 Capítulos de libros
1: (2007)
Advances in materials physics for IFE at DENIM
2: (2007)
Advances in target design and materials physics for IFE at DENIM
3: (2007)
Comparison of Monte Carlo neutron transport codes and Nuclear Data libraries for neutron calculations in different IFE concepts
4: (2007)
Impact of activation cross section uncertainties on the waste management performance of irradiated steels under different neutron environments of IFE Thick-Liquid concepts
5: (2007)
Safety and environmental analysis for fusion facilities: Methodologies and Applications
6: (2007)
Safety and environmental considerations for laser IFE chambers
7: (2008)
Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE structural materials
8: (2008)
3D neutronic calculations: CAD-MCNP methodology applied to vessel activation in KOYO-F
9: (2016)
Results of UPM and CSN for the Burn-up Credit Criticality Safety Benchmark Phase III-C
3 Conferencias invitadas en congresos
1: (2009)
EFF/EAF Meeting NEA
2: (2009)
IAEA Technical Meeting in colaboration with NEA on Specific Applications of Research Reactor: Provision of Nuclear Data.
3: (2011)
Impact of Nuclear Data Uncertainties in the Phase-1B Benchmark
16 Cursos, seminarios y tutoriales
1: (2010)
Lesson 1. Improvements in the prediction capability of activation codes: Error propagation of nuclear data uncertainty. Examples
2: (2010)
Lesson 2. Nuclear data requirements for ADS: Uncertainty and sensitivity study
3: (2010)
Lesson 3. Exercises with ACAB code. Examples¿
4: (2012)
Calculations of Fission Pulse Neutron Emission: A comparison between JEFF-3.1.1. and ENDF/B-VII.1
5: (2012)
IMPORTANCE OF NUCLEAR DATA UNCERTAINTIES IN CRITICALITY AND BURNUP CALCULATIONS FOR LWR
6: (2012)
Presentation and discussion of submitted results for Exercise 1b: ?Pin cell burnup benchmark
7: (2012)
Processing of the JEFF-3.1.2 Cross Section Library into various formats (ACE, PENDF, GENDF, MATXSR and BOXER) for testing purposes
8: (2012)
TASK 2.4 Covariances for activation, radioactive decay and fission yields
9: (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)
10: (2018)
Example of a Bayesian Monte Carlo (BMC) Technique applied for 235U adjustment using Criticality and Transmission Integral Benchmarks
11: (2018)
JEFF Processing, Verification, Benchmarking and Validation Meeting: Introduction.
12: (2018)
On the International Radiation Characterization Benchmarks Experiment Project (IRCBEP): User s Point of View
13: (2018)
Recent Updates to the Nuclear Data Sensitivity Tool (NDaST),
14: (2018)
Upgraded SEANAP-PWR core simulator with JEFF-3.3: Impact of Nuclear Data Uncertainties for PWR Cycle Operation
15: (2018)
WPNCS-SG3 Benchmark on the effect of temperature on the keff for PWR fuel assemblies and Computational Benchmark for the Doppler Reactivity Defect,
16: (2019)
The importance of nuclear data for nuclear applications and the JEFF Project' (A.Plompen, JRC/EU)
1 Libros
1: (2007)
29th International Conference on Laser Interaction with Matter
21 Otras Publicaciones
1: (2008)
International Conference on the Physics of Reactors "Nuclear Power: A Sustainable Resource" (PHYSOR 08)
2: (2013)
Accurate Nuclear Data for nuclear Energy Sustainability
3: (2013)
Accurate Nuclear Data for nuclear Energy Sustainability
4: (2019)
A comparison of ENDF/B-VIII.0 to some other evaluations for different criticality calculations in thermal systems.
5: (2019)
P&V of JEFF-3.3 by Using FRENDY Code
6: (2019)
Resumen de las Jornadas de Usuarios de Datos Nucleares y JEFF Stakeholders meeting T
7: (2019)
UPM contribution to WPEC/SG47
8: (2019)
Actividades de la OECD/NEA,
9: (2019)
Actividades de la OECD/NEA
10: (2019)
Comparison of JEFF-3.3 and ENDF/B-VIII.0 in PWR simulations
11: (2019)
Current activities on Processing and Verification (P&V) at Universidad Politécnica de Madrid
12: (2019)
Experiencia de datos nucleares en simulaciones PWR
13: (2019)
First feedback on using FRENDY for processing of JEFF-3.3
14: (2019)
OECD/NEA WPEC SG 46: ''Joint CIEMAT and UPM contribution: ASTRID, ALFRED and MYRRHA''
15: (2019)
OECD/NEA WPEC SG 46: ''Status on MYRRHA, ESFR, ASTRID and ALFRED''
16: (2019)
Organización por la OECD/NEA del JEFF Stakeholders Meeting
17: (2019)
Resumen de Actividades y propuesta de nuevas por la UPM.
18: (2019)
Status on MYRRHA, ESFR, ASTRID and ALFRED
19: (2019)
UPM contribution to ACTION 6: 'Revision of TAR tables'
20: (2019)
UPM/IAEA contributions to inter-comparison study
21: (2019)
WPEC/SG40: An Extended Summary of the Collaborative International Evaluated Library Organisation (CIELO) Pilot Project.7498,
80 Ponencia en Congresos
1: (2007)
Application of Monte Carlo Techniques for Propagation of Cross Section Uncertainties to Actinide Inventory in ADS Transmuters: Comparison with Sensitivity Analysis
2: (2007)
Assessment of Uncertainties in the Prediction of Actinide Inventory in Accelerator-Driven Transmutation Dedicated Systems
3: (2007)
Cámaras de fisión miniaturizadas para medidas neutrónicas en IFMIF
4: (2007)
Effect of Activation Cross Section Uncertainties in Transmutation Analysis of Realistic Low-Activation Steels for IFMIF
5: (2007)
Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
6: (2007)
Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
7: (2007)
Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE structural materials
8: (2007)
Processing and validation of JEFF3.1 library in ACE format at 10 different temperatures
9: (2007)
3D Neutronic Calculations: CAD-MCNP Methodology applied to Vessel Activation in KOYO-F
10: (2008)
Feasibility of a neutron diagnostic for the IFMIF test cell
11: (2008)
Impact of different correlation structures in cross-section covariance matrices on the inventory and inventory-related parameters
12: (2008)
Progress in Inertial Fusion and Fusion Technology at DENIM
13: (2008)
Target Physics and Materials for Inertial Fusion and Fusion Technology at DENIM
14: (2009)
Impact of activation cross section uncertainties on the tritium production in the HFTM specimen cells
15: (2009)
Impact of activation cross section uncertainties on the tritium production in the HFTM specimen cells
16: (2009)
Improvements in the Prediction Capability of ACAB Code to Transmutation Analysis in IFMIF
17: (2009)
Improvements in the Prediction Capability of Codes Used to Design Innovative Reactors
18: (2010)
Assessment of fissionable material behaviour in fission chambers
19: (2010)
Education and Training of Future Nuclear Engineers at DIN: From Advanced Computer Codes to an Interactive Plant Simulator
20: (2010)
EDUCATION AND TRAINING OF FUTURE NUCLEAR ENGINEERS THROUGH THE USE OF AN INTERACTIVE PLANT SIMULATOR
21: (2010)
Keff Sensitivity/Uncertainty Analysis of the Phase VII Burnup Credit Benchmark
22: (2010)
Neutron Cross-Section Covariances: Users' perspectives
23: (2010)
PROPAGATION OF NUCLEAR DATA UNCERTAINTIES IN TRANSMUTATION CALCULATIONS USING ACAB CODE
24: (2011)
A Comparison of different Uncertainty Activation Cross-Section Data Libraries and collapsed values for different neutron spectra: ADS, FISSION and FUSION
25: (2011)
A Comparison of diffferent Uncertainty Activation Cross-Section Data Libraries: Application to the Prediction Uncertainty in Tritium Production
26: (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
27: (2011)
Analysis of different uncertainty activation cross section data libraries for LWR, ads and demo neutron spectra
28: (2011)
Burnup Uncertainty Analysis for PWR-HFP Exercise I-1
29: (2011)
Formación y entrenamiento de ingenieros nucleares mediante el máster de Ciencia y Tecnología nuclear de la UPM
30: (2011)
Importance of Nuclear Data Uncertainties in Criticality Calculations
31: (2011)
Isotopic prediction calculation methodologies: application to Vandellos-II Reactor cycles 7-11
32: (2011)
Isotopic prediction simulations applied to high burnup samples irradiated in VANDELLÓS-II Reactor core
33: (2011)
Isotopic uncertainty assessment due to nuclear data uncertainties in high-burnup samples
34: (2011)
Propagation of nuclear data uncertainties in fuel cycle calculations using MONTE-CARLO Technique
35: (2011)
Uncertainty assessment methodologies applied to Tritium production in fusion lithium breeding blankets
36: (2011)
Uncertainty methods inactivation and inventory calculations
37: (2011)
Updated Co-58 evaluation for background capture reaction (MT102) (JEF/DOC-1367)
38: (2011)
UPM Results BWR-PWR Exercise I-1 by MCNP5 code
39: (2012)
Processing of the JEFF-3.1.2 Cross Section Library into various formats (ACE, PENDF, GENDF, MATXSR and BOXER) for testing purposes
40: (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)
41: (2013)
Analysis of Neutron Thermal Scattering Data Uncertainties in PWRs
42: (2013)
Analysis of the Quality of Evaluated Data for Most Relevant Reactions of MYRRHA
43: (2013)
Application of a Bayesian/Generalised Least-Squares method to generate correlations between independent neutron fission yield data
44: (2013)
Generation of a complete damage energy cross-section library up to 150 MeV based on JEFF -3.1.1
45: (2013)
Generation of Fission Yield covariance data and application to Fission Pulse Decay Heat calculations (JEF/DOC-1520)
46: (2013)
GRS Results for the Burnup Pin-cell Benchmark Propagation of Cross-Section, Fission Yields and Decay Data Uncertainties
47: (2013)
Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and Their Irradiated Fuel. Comparison between Libraries
48: (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
49: (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
50: (2013)
Processing and generation of DPA cross section library up to 150 MeV (EFFDOC-1203)
51: (2013)
Processing and validation of JEFF3.1.2 cross-section library into various formats: ACE, PENDF, GENDF, MATXSR and BOXER
52: (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
53: (2013)
Processing of the JEFF-3.2T3 Cross Section Library with the NJOY Code System into Various Formats for Testing Purposes
54: (2013)
Progress on Spent Fuel Data Compilations at UPM Octubre 8-9, 2013
55: (2013)
Propagation of Neutron Cross Section, Fission Yield, and Decay Data Uncertainties in Depletion Calculations
56: (2013)
Propagation of U235-238, Pu239 and STL Nuclear Data Uncertainties for PWR core analysis (JEF/DOC-1524)
57: (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
58: (2013)
The Nuclear Science and Technology master at the Universidad Politecnica de Madrid
59: (2013)
Thermal Scattering Libraries Processing (F4E, Task 6.2)
60: (2013)
Towards a complete propagation of nuclear data uncertainties Fission yields and decay data
61: (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
62: (2013)
UPM activities on: Nuclear Data (processing), Activation-Source Term Calculation and Uncertainty Propagation
63: (2013)
UPM Activities on Sensitivity and Uncertainty Analysis of Assembly Depletion Abril 10-12, 2013
64: (2013)
UPM Activities on the generation of DPA cross section library up to 150 MeV (Task 4.1)
65: (2014)
Impact of the Fission Yield Covariance Data in Burn-up Calculations (JEF/DOC-1566)
66: (2014)
IMPACT OF THE FISSION YIELD NUCLEAR DATA UNCERTAINTIES IN THE PIN-CELL BURN-UP OECD/NEA UAM BENCHMARK
67: (2014)
Nuclear Data Uncertainty Propagation in Depletion Calculations of Advanced Reactor Systems with Comparison of Using One-group or Multigroup Cross-Sections
68: (2014)
Processing of the new JEFF-3.2T4 Cross Section Library with the NJOY Code System into Various Formats for Testing Purposes
69: (2014)
Propagation of U-235. U-238, Pu-239 and H in H2O nuclear data uncertainties for PWR core analysis
70: (2014)
SENSITIVITY/UNCERTAINTY ANALYSIS FOR BWR CONFIGURA-TIONS OF EXERCISE I-2 OF UAM BENCHMARK
71: (2014)
Student oportunities in the frame of the European Project GENTLE
72: (2016)
Nuclear data sensitivity analysis and evaluated data library comparison for MYRRHA relevant quantities
73: (2017)
Neutron-induced nuclear data for the MYRRHA fast spectrum facility
74: (2017)
Neutron-induced nuclear data for the MYRRHA fast spectrum facility
75: (2017)
Neutron-induced nuclear data for the MYRRHA fast spectrum facility
76: (2017)
Neutron-induced nuclear data for the MYRRHA fast spectrum facility
77: (2018)
Examples of Monte Carlo Techniques Applied for Nuclear Data Uncertainty Propagation, WONDER2018
78: (2019)
CDIO Course Development for Design and Simulation of PWRs
79: (2019)
Comparison of JEFF-3.3 and ENDF/B-VIII.0 Nuclear Data Libraries in PWR Simulations
80: (2019)
Use of Shielding Integral Benchmark Archive and Database for Nuclear Data Validation
Explotación de Resultados y Transferencia de Tecnología
2 Registros de Software
1: (2014)
Thermal Scattering Libraries processed to ACE format. NEA-1883 ZZ-TSL-ACE/2013
2: (2014)
Thermal Scattering Libraries processed to ACE format. RSICC DATA LIBRARY DLC-270.
• TOMA DE DATOS DE MEMORIAS Y CV
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S2i 2023 Observatorio de investigación @ UPM con la colaboración del Consejo Social UPM
Cofinanciación del MINECO en el marco del Programa INNPACTO (IPT-020000-2010-22)
