Observatorio de I+D+i UPM
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RESEARCHERS
RDI STRUCTURES
RESEARCH ACTIVITIES
INNOVATION
Investigador
Jose Maria Aragones Beltran
Researcher Category
CATEDRATICO UNIVERSIDAD
UPM Centre
E.T.S. DE INGENIEROS INDUSTRIALES
Department:
INGENIERIA NUCLEAR
Research Centre/Institute
INSTITUTO DE FUSION NUCLEAR
Knowledge Area
INGENIERIA NUCLEAR
Research Group:
Sin grupo de investigación
Email
jose.m.aragones
upm.es
Researcher isn't working at UPM
Research Reports
Proyectos de I+D+i y generación de recursos
10 Proyectos de I+D+i
1: (2007)
European Plataform for Nuclear Reactor Simulations NURESIM
2: (2007)
Sustainable nuclear fission technology platform, SNF-TP
3: (2008)
European Plataform for Nuclear Reactor Simulations NURESIM
4: (2008)
Sustainable Nuclear Fission Technology Platform SNF-TP
5: (2009)
CP-ESFR: Collaborative Project on the European Sodium Fast Reactor.
6: (2009)
NURISP: NUCLEAR REACTOR INTEGRATED SIMULATION PROJECT Nº 232124
7: (2011)
CP-ESFR: Collaborative Project on European Sodium Fast Reactor
8: (2011)
HIPER (1): European High Power Laser Energy Research Facility
9: (2011)
HIPER (1): European High Power Laser Energy Research Facility
10: (2011)
NURISP: Nuclear Reactor Integrated Simulation Project
Formación de Investigadores y Movilidad
2 Tesis Doctorales
1: (2007)
ANÁLISIS TERMOHIDRÁULICO DE NÚCLEOS PWR CON MODELIZACIÓN DE FLUJO BIFÁSICO PARA ACOPLAMIENTO CON LA NEUTRÓNICA
2: (2007)
Análisis termohidráulico de núcleos PWR con modelización de flujo bifásico para acoplamiento con la neutrónica
Difusión de Resultados de Investigación
9 Artículos en revistas
1: (2007)
The Analytic Coarse-Mesh Finite Difference Method for Multigroup and Multidimensional Diffusion Calculations
2: (2008)
Participación española en el desarrollo de la Plataforma Europea para Simulación de Reactores Nucleares (NURESIM)
3: (2008)
The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: Development and performance analysis
4: (2009)
A domain decomposition methodology for pin by pin coupled neutronic and thermal-hydraulic analyses in COBAYA3
5: (2009)
Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
6: (2010)
A domain decomposition methodology for pin by pin coupled neutronic and thermal-hydraulic analyses in COBAYA3
7: (2010)
Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
8: (2010)
Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis
9: (2011)
Education and Training of Future Nuclear Engineers Through the use of an Interactive Plant Simulator
5 Capítulos de libros
1: (2007)
Development and Performance of the Analytic Nodal Diffusion Solver ANDES in Multigroups for 3D Rectangular Geometry
2: (2007)
3D Whole Core Fine Mesh Multigroup Diffusion Calculations by Domain Decomposition through Alternate Dissections
3: (2008)
Basis for Coupled 3-D Neutronics-Thermal-Hydraulics
4: (2008)
“Fundamentals of 3-D Neutron Kinetics and Current Status”
5: (2008)
“Nuclear Power Feasibility 2007”
1 Cursos, seminarios y tutoriales
1: (2008)
Perspectiva de la Física y Energía Nuclear
3 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 pin-by-pin/nodal scope multigroup diffusion COBAYA3 code for steady-state and transient problems in 3D rectangular geometry”
3: (2008)
”Report and sample/test problems for use of the advanced core- lattice methods integrated into the NURESIM common package by linking via SALOME”
2 Libros
1: (2007)
Nuclear Power Feasibility 2007
2: (2007)
The Sustainable Nuclear Energy Technology Platform: A Vision Report
9 Otras Publicaciones
1: (2008)
Objectives and Goals Priorities in Scientific Scope”
2: (2008)
“Agenda of the NURESIM Workshops and Final Seminar”
3: (2008)
“NURESIM Core Physics Benchmarking Overview”
4: (2008)
“NURESIM WP1.2 Deterministic Lattice and Core Codes main results and demonstrations”
5: (2008)
“Overview of NURESIM SP1 Core Physics SubProject results and upcoming developments”
6: (2008)
“Overview of NURESIM SP1 SubProject Core Physics main results and demonstrations”
7: (2008)
“Registration of Attendance and Organization of the NURESIM Workshops and Seminar”
8: (2008)
“Review of NURESIM-SP1 Core Physics Subproject and Plans for Extension in 2008”
9: (2008)
”Integration of ANDES and COBAYA in SALOME”
12 Ponencia en Congresos
1: (2007)
Development and Performance of the Analytic Nodal Diffusion Solver ANDES in Multigroups for 3D Rectangular Geometry
2: (2007)
Multiscale and Multiphysics Coupling in COBAYA3
3: (2007)
The Integrated 3-D PWR Core Analysis System SEANAP
4: (2008)
Descomposición espacial en subdominios para reactores de agua ligera a la escala de la barra de combustible
5: (2008)
Development of an Analytic Nodal Diffusion Solver in Multigroups for 3D Reactor Cores with Rectangular or Hexagonal Assemblies.
6: (2008)
Transient analysis in the 3D nodal kinetics and thermal-hydraulics ANDES/COBRA coupled system
7: (2009)
DEVELOPMENT AND PERFORMANCE OF THE ANDES/COBRA-III COUPLED SYSTEM IN HEXAGONAL-Z GEOMETRY
8: (2009)
PERFORMANCE OF WHOLE CORE PIN-BY-PIN CALCULATIONS BY DOMAIN DECOMPOSITION THROUGH ALTERNATE DISSECTIONS IN STEADY STATE AND TRANSIENT CALCULATIONS
9: (2010)
Aplicación del código COBAYA3 al análisis multiescala con acoplamiento neutrónico-termohidráulico en reactores PWR
10: (2010)
Education and Training of Future Nuclear Engineers at DIN: From Advanced Computer Codes to an Interactive Plant Simulator
11: (2010)
EDUCATION AND TRAINING OF FUTURE NUCLEAR ENGINEERS THROUGH THE USE OF AN INTERACTIVE PLANT SIMULATOR
12: (2010)
Whole Core Pin-by-Pin Coupled Neutronic-Thermal-hydraulic Steady state and Transient Calculations using COBAYA3 code
Explotación de Resultados y Transferencia de Tecnología
1 Patentes
1: (2007)
Co-autores del Sistema SEANAP: Sistema Español de Análisis de Nucleos de reactores de Agua a Presión.
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