Observatorio de I+D+i UPM
• ESPAÑOL
• ENGLISH
INVESTIGADORES
ESTRUCTURAS DE I+D+I
ACTIVIDAD INVESTIGADORA
INNOVACIÓN
Investigador
Nuria Garcia Herranz
Categoría Investigador
TITULAR UNIVERSIDAD
Escuela UPM
E.T.S. DE INGENIEROS INDUSTRIALES
Departamento:
INGENIERÍA ENERGÉTICA (N)
Centros/Institutos I+D+i
INSTITUTO DE FUSION NUCLEAR GUILLERMO VELARDE
Area Conocimiento
INGENIERIA NUCLEAR
Grupo de Investigación:
Ciencia y Tecnología de sistemas avanzados de fisión nuclear
Email (Directorio UPM)
nuria.garcia.herranz
upm.es
Teléfono (Directorio UPM)
910677127
Datos de Memorias relacionados
Proyectos de I+D+i y generación de recursos
46 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)
CP-ESFR: Collaborative Project on the European Sodium Fast Reactor.
4: (2009)
CREDITO AL QUEMADO EN LOS ANALISIS DE SEGURIDAD FRENTE A CRITICIDAD
5: (2009)
NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
6: (2010)
CP-ESFR: COLLABORATIVE PROJECT ON EUROPEAN SODIUM FAST REACTOR PROJECT Nº 232658
7: (2010)
NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
8: (2011)
ANDES: Accurate Nuclear Data for nuclear Energy Sustainability
9: (2011)
CP-ESFR: Collaborative Project on European Sodium Fast Reactor
10: (2011)
NURISP: Nuclear Reactor Integrated Simulation Project
11: (2013)
CHANDA (Solving Challenge in Nuclear Data)
12: (2013)
CHANDA: solving CHAllenges in Nuclear DAta
13: (2013)
ESNII plus: Preparing ESNII for HORIZON 2020
14: (2013)
ESNII plus: Preparing ESNII for Horizon 2020
15: (2013)
GENTLE: Graduate and Executive Nuclear Training and Lifelong Education
16: (2013)
GENTLE: Graduate and Executive Nuclear Training and Lifelong Education
17: (2013)
NURESAFE: NUCLEAR REACTOR SAFETY SIMULATION PLATFORM
18: (2013)
NURESAFE: NUCLEAR REACTOR SAFETY SIMULATION PLATFORM Grant Agreement no: 323263
19: (2013)
NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
20: (2014)
ANDES - 249671
21: (2014)
ÁREA DE CRÉDITO AL QUEMADO EN LOS ANÁLISIS DE SEGURIDAD FRENTE A CRTICIDAD
22: (2014)
CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
23: (2014)
COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
24: (2014)
ESNII PLUS( PREPARING ESNII FOR HORIZON 2020)
25: (2014)
NURESAFE-323263
26: (2014)
NURESAFE-323263
27: (2015)
ANDES - 249671
28: (2015)
CÁTEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
29: (2015)
COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
30: (2015)
CP-ESFR: COLLABORATIVE PROJECT ON EUROPEAN SODIUM FAST REACTOR PROJECT Nº 232658
31: (2015)
NUCLEAR DATA IMPROVEMENTS AND DEVELOPMENT OF TOOLS-NUCLEAR DATA EVALUATION
32: (2016)
CÁTEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
33: (2016)
COLABORACIÓN EN EL ÁREA DE LA PROPAGACIÓN DE INCERTIDUMBRES EN LOS CÁLCULOS NEUTRÓNICOS
34: (2016)
PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
35: (2017)
ESFR-SMART: European Sodium Fast Reactor Safety Measures Assessment and Research Tools
36: (2017)
European Sodium Fast Reactor Safety Measures Assessment and Research Tools (ESFR-SMART)
37: (2017)
PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
38: (2018)
CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
39: (2018)
ESNII PLUS( PREPARING ESNII FOR HORIZON 2020)
40: (2018)
Responsable del Proyecto Propio: Desarrollo de un sistema BEPU para la simulación de reactores PWR
41: (2019)
CATEDRA DE SEGURIDAD NUCLEAR FEDERICO GODED
42: (2019)
CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
43: (2019)
CHANDA: SOLVING CHALLENGES IN NUCLEAR DATA
44: (2019)
PREVENCION Y GESTION DE SECUENCIAS DE ACCIDENTE SEVERO EN REACTORES AVANZADOS Y CONVENCIONALES (PYGAS)
45: (2019)
Responsable del Proyecto Propio: Desarrollo de un sistema BEPU para la simulación de reactores PWR
46: (2019)
SANDA (Supplying Accurate Nuclear Data for Energy and Non-Energy Applications)
Formación de Investigadores y Movilidad
6 Tesis Doctorales
1: (2010)
Desarrollo de un Código anatítico de difusión neutrónica en multigrupos para reactores en geometrías 3D rectangulares y Hexagonales
2: (2013)
Tesis Raquel Ochoa Valero:
3: (2017)
Generación de librerias optimizadas con cuantificaccion de incertidumbres para claculos realistas de reactores nucleares de agua ligera
4: (2018)
Methodologies for sensitivity/uncertainty analysis using reactor core simulators with application to PWR
5: (2018)
Methodologies for sensitivity/uncertainty analysis using reactor core simulators with application to PWR
6: (2019)
Nuclear Data Analyses for Improving the Safety of Advanced Lead-cooled Reactors
Difusión de Resultados de Investigación
54 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)
The Analytic Coarse-Mesh Finite Difference Method for Multigroup and Multidimensional Diffusion Calculations
3: (2008)
Participación española en el desarrollo de la Plataforma Europea para Simulación de Reactores Nucleares (NURESIM)
4: (2008)
Propagation of Statistical and Nuclear Data Uncertainties in Monte-Carlo Burn-up Calculations
5: (2008)
The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: Development and performance analysis
6: (2009)
Effect of activation cross section uncertainties in the assessment of primary damage for MFE/IFE low-activation steels irradiated in IFMIF
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)
Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
9: (2010)
Assessment of fissionable material behaviour in fission chambers
10: (2010)
Assessment of fissionable material behaviour in fission chambers
11: (2010)
Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
12: (2010)
Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
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)
Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
22: (2011)
Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
23: (2012)
Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR
24: (2013)
A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
25: (2013)
A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
26: (2013)
A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
27: (2013)
A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides
28: (2014)
Educating Nuclear Engineers by Nuclear Science and TEchnology Master at UPM
29: (2014)
Effects of cross sections tables generation and optimization on rod ejection transient analyses
30: (2014)
Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
31: (2014)
Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
32: (2014)
Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
33: (2014)
Optimization of multidimensional cross-section tables for few-group core calculations
34: (2016)
Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference
35: (2016)
Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference
36: (2016)
Improving PWR core simulations by Monte Carlo uncertainty analysis and Bayesian inference
37: (2017)
Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
38: (2017)
Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
39: (2017)
Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
40: (2017)
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
41: (2017)
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
42: (2017)
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
43: (2017)
Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations
44: (2017)
Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core
45: (2017)
Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
46: (2017)
Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
47: (2017)
Testing the NURESIM platform on a PWR main steam line break benchmark
48: (2017)
Testing the NURESIM platform on a PWR main steam line break benchmark
49: (2018)
Impact of the homogenization level, nodal or pin-by-pin, on the uncertainty quantification with core simulators
50: (2018)
Impact of the homogenization level, nodal or pin-by-pin, on the uncertainty quantification with core simulators
51: (2018)
Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for pin-by-pin PWR transient analysis
52: (2018)
Stress-testing the ALFRED design - Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients
53: (2019)
Nuclear data analyses for improving the safety of advanced lead-cooled reactors
54: (2019)
Sensitivity methods for effective delayed neutron fraction and neutron generation time with summon
2 Capítulos de libros
1: (2007)
Development and Performance of the Analytic Nodal Diffusion Solver ANDES in Multigroups for 3D Rectangular Geometry
2: (2016)
Results of UPM and CSN for the Burn-up Credit Criticality Safety Benchmark Phase III-C
4 Conferencias invitadas en congresos
1: (2009)
IAEA Technical Meeting in colaboration with NEA on Specific Applications of Research Reactor: Provision of Nuclear Data.
2: (2016)
Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like Sodium Fast Reactor
3: (2017)
Overview of the UPM-CSN activities for Uncertainty Quantification in PWR full core simulations
4: (2017)
Overview of the UPM-CSN activities for Uncertainty Quantification in PWR full core simulations
2 Cursos, seminarios y tutoriales
1: (2016)
GENTLE Intersemester Course on Nuclear Data Processing and Use in Nuclear Applications
2: (2018)
ESFR-SMART Workshop on Liquid Metal Facilities: Nuclear data Sensitivity/Uncertainty Analysis in Nuclear Applications
2 Informes para las AAPP o sus organismos dependientes
1: (2008)
”Final Report and sample test problems for use of the core scope COBAYA3 / ANDES code in steady-state/eigenvalue and transient/source problems of multi-group diffusion for 3D rectangular and hexagonal-triangular geometries integrated in the common NURESIM platform”
2: (2008)
”Report and sample/test problems for use of the advanced core- lattice methods integrated into the NURESIM common package by linking via SALOME”
9 Otras Publicaciones
1: (2008)
”Integration of ANDES and COBAYA in SALOME”
2: (2011)
Report on the results of PWR benchmarks using COBAYA3 and DYN3D pin-by-pin
3: (2012)
Definition and development of the automated pre- and post-processing procedures and codes to generate advanced cell and nodal XS libraries for PWR, BWR and VVER, covering the full parameter space of operation, burn-up and transient conditions
4: (2012)
Definition and tools for Advanced Cell and Nodal Cross Section Libraries and Definition of the interface between APOLLO2 and DYN3D and COBAYA3
5: (2019)
Benchmarking KENO-VI against MCNP/Serpent using a simplified SFR pin-cell problem
6: (2019)
D1.2.1. Initial core performance and burnup calculations
7: (2019)
OECD/NEA WPEC SG 46: ''Joint CIEMAT and UPM contribution: ASTRID, ALFRED and MYRRHA''
8: (2019)
OECD/NEA WPEC SG 46: ''Status on MYRRHA, ESFR, ASTRID and ALFRED''
9: (2019)
Status on MYRRHA, ESFR, ASTRID and ALFRED
89 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)
Development and Performance of the Analytic Nodal Diffusion Solver ANDES in Multigroups for 3D Rectangular Geometry
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)
The Integrated 3-D PWR Core Analysis System SEANAP
7: (2008)
Descomposición espacial en subdominios para reactores de agua ligera a la escala de la barra de combustible
8: (2008)
Development of an Analytic Nodal Diffusion Solver in Multigroups for 3D Reactor Cores with Rectangular or Hexagonal Assemblies.
9: (2008)
Impact of different correlation structures in cross-section covariance matrices on the inventory and inventory-related parameters
10: (2008)
Transient analysis in the 3D nodal kinetics and thermal-hydraulics ANDES/COBRA coupled system
11: (2009)
DEVELOPMENT AND PERFORMANCE OF THE ANDES/COBRA-III COUPLED SYSTEM IN HEXAGONAL-Z GEOMETRY
12: (2009)
Impact of activation cross section uncertainties on the tritium production in the HFTM specimen cells
13: (2009)
Impact of activation cross section uncertainties on the tritium production in the HFTM specimen cells
14: (2009)
Improvements in the Prediction Capability of ACAB Code to Transmutation Analysis in IFMIF
15: (2009)
Improvements in the Prediction Capability of Codes Used to Design Innovative Reactors
16: (2010)
Análisis de la transmutación de Actínidos Minoritarios en un reactor rápido de sodio con modelo de carga homogéneo mediante el código MCNPX-CINDER
17: (2010)
Aplicación del código COBAYA3 al análisis multiescala con acoplamiento neutrónico-termohidráulico en reactores PWR
18: (2010)
Education and Training of Future Nuclear Engineers at DIN: From Advanced Computer Codes to an Interactive Plant Simulator
19: (2010)
EDUCATION AND TRAINING OF FUTURE NUCLEAR ENGINEERS THROUGH THE USE OF AN INTERACTIVE PLANT SIMULATOR
20: (2011)
A proposed parameterization of interface discontinuity factors depending on neighborhood for pin-by-pin diffusion computations for LWR
21: (2011)
Formación y entrenamiento de ingenieros nucleares mediante el máster de Ciencia y Tecnología nuclear de la UPM
22: (2011)
Interactive graphic simulation: an advanced methodology to improve the teaching-learning process in nuclear engineering education and training
23: (2011)
Interface discontinuity factors in the modal eigenspace of the multigroup diffusion matrix
24: (2011)
On the extension of the analytic nodal solver ANDES to sodium fast reactors
25: (2012)
Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project
26: (2012)
Boron dilution benchmark using COBAYA3/FLICA4 coupled codes within the NURISP European Project
27: (2012)
Development of the neutronic/thermal-hydraulic coupling between COBAYA3 and SUBCHANFLOW. Aplication to Sodium Fast reactors
28: (2012)
Initiatives and facilities for E&T in the nuclear science and technology master at UPM
29: (2012)
Initiatives and facilities for E&T in the nuclear science and technology master at UPM
30: (2012)
Optimización de librerías tabuladas de secciones eficaces mediante el empleo de coeficientes de sensibilidad
31: (2012)
Optimización de librerías tabuladas de secciones eficaces mediante el empleo de coeficientes de sensibilidad
32: (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
33: (2013)
Nuclear data uncertainty propagation to reactivity coefficients of Sodium Fast Reactor
34: (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
35: (2013)
The Nuclear Science and Technology master at the Universidad Politecnica de Madrid
36: (2013)
UPM Activities on Sensitivity and Uncertainty Analysis of Assembly Depletion Abril 10-12, 2013
37: (2014)
DESARROLLO DE UNA HERRAMIENTA DE VERIFICACIÓN PARA CÁLCULOS DE DIFUSIÓN MEDIANTE COBAYA
38: (2014)
Desarrollo de una herramienta de verificación para cálculos de difusión mediante COBAYA
39: (2014)
EFECTOS DE GENERACIÓN Y OPTIMIZACIÓN DE LIBRERÍAS DE SECCIONES EFICACES EN EL ANÁLISIS DE TANSITORIOS EN REACTORES PWR
40: (2014)
Efectos de generación y optimización de librerias de secciones eficaces en ela nalisis de transitorios en reactores PWR
41: (2014)
SENSITIVITY/UNCERTAINTY ANALYSIS FOR BWR CONFIGURA-TIONS OF EXERCISE I-2 OF UAM BENCHMARK
42: (2014)
Student oportunities in the frame of the European Project GENTLE
43: (2015)
Covariances matrices of few-group homogeneized cross sections for core diffusion calculations
44: (2015)
Covarianzas de las secciones eficaces homogeneizadas en dos grupos de energía para cálculos de difusión
45: (2015)
European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients
46: (2015)
IMPACT OF NUCLEAR DATA UNCERTAINTIES ON THE REACTIVITY OF AN ASTRID-LIKE SODIUM FAST REACTOR
47: (2015)
Metodologías de propagación de incertidumbres con el código de difusión COBAYA
48: (2015)
Metodologías de propagación de incertidumbres con el código de difusión COBAYA
49: (2015)
SPANISH CONTRIBUTION IN THE DESIGN OF THE ALFRED REACTOR INSIDE THE ESNII+ Project
50: (2015)
Spanish contribution in the design of the ASTRID reactor inside the ESNII+ Project
51: (2015)
Uncertainty propagation techniques for reactor core calculations using COBAYA code
52: (2015)
Uncertainty propagation techniques for reactor core calculations using COBAYA code
53: (2016)
: Coolant materials description in the new JEFF-3.3T1 for GEN-IV reactors
54: (2016)
Coolant materials description in the new JEFF-3.3T1 for GEN-IV reactors
55: (2016)
Coolant materials description in the new JEFF-3.3T1 for GEN-IV reactors
56: (2016)
Exercise I-3: Comparison of uncertainty propagation in nodal and pin-by-pin calculations using COBAYA code
57: (2016)
Impact of fuel modeling and TH uncertainties in a MSLB scenario
58: (2016)
Nuclear data sensitivity analysis and evaluated data library comparison for MYRRHA relevant quantities
59: (2016)
Nuclear data sensitivity analysis and evaluated data library comparison for MYRRHA relevant quantities
60: (2016)
Nuclear Data Uncertainties for typical fuel assemblies and a simple reactor core
61: (2016)
Preparing uncertainty quantification in multi-physics and multi-scale core simulations using COBAYA and CTF codes
62: (2016)
Sensitivity and Uncertainty analysis of MYRRHA lead-bismuth cooled fast reactor
63: (2016)
Sensitivity and Uncertainty analysis of MYRRHA lead-bismuth cooled fast reactor
64: (2016)
Thermal-hydraulic uncertainty propagation in a Main Steam Line Break Scenario
65: (2016)
Thermal-hydraulic uncertainty propagation in a Main Steam Line Break Scenario
66: (2017)
Análisis de las incertidumbres en los factores de pico de un núcleo PWR
67: (2017)
Análisis de las incertidumbres en los factores de pico de un núcleo PWR
68: (2017)
Coupled calculations COBAYA4/CTF for different MSLB scenarios in the frame of NURESAFE project
69: (2017)
Impact of nuclear data uncertainties on the reactivity coefficients of ALFRED
70: (2017)
Neutron-induced nuclear data for the MYRRHA fast spectrum facility
71: (2017)
Neutron-induced nuclear data for the MYRRHA fast spectrum facility
72: (2017)
Neutron-induced nuclear data for the MYRRHA fast spectrum facility
73: (2017)
Neutron-induced nuclear data for the MYRRHA fast spectrum facility
74: (2017)
Nuclear Data sensitivity and uncertainty assessment of the sodium voiding reactivity coefficients pf an ASTRID-like sodium fast reactor
75: (2017)
Results for Exercise I-3 with COBAYA: Analysis of the peaking power factors
76: (2017)
Validation of COBAYA4/CTF coupling within European NURESIM Platform against MCNP/CTF
77: (2018)
Conceptual design of the ESFR reactor core catcher in the ESFR-SMART project
78: (2018)
Methodologies for Sensitivity/Uncertainty Analysis Using Reactor Core Simulators with Application to Pressurized Water Reactors
79: (2018)
Nuclear data analyses for improving the safety of advanced lead-cooled reactors
80: (2018)
Nuclear data analyses for improving the safety of advanced lead-cooled reactors
81: (2018)
Sensitivity and Uncertainty Methods for Effective Delayed Neutron Fraction and Neutron Generation Time With Summon
82: (2018)
Spanish contribution to the Superphénix reactor benchmark for neutronics validation
83: (2018)
Spanish contribution to the Superphénix reactor benchmark for neutronics validation
84: (2019)
About the impact of the Unresolved Resonance Region in Monte Carlo simulations of Sodium Fast Reactors
85: (2019)
About the impact of the Unresolved Resonance Region in Monte Carlo simulations of Sodium Fast Reactors
86: (2019)
Active learning in reactor physics using state-of-the-art simulation tools at Universidad Politécnica de Madrid
87: (2019)
Horizon-2020 ESFR-SMART project on Sodium Fast Reactor Safety: status after 18 months
88: (2019)
Identificación y modelización de experimentos de criticidad en apoyo a la validación del código de transporte neutrónico de Monte Carlo KENO-VI/SCALE y bases de datos asociadas
89: (2019)
Nuclear data assimilation for MYRRHA
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S2i 2022 Observatorio de investigación @ UPM con la colaboración del Consejo Social UPM
Cofinanciación del MINECO en el marco del Programa INNPACTO (IPT-020000-2010-22)
