Items where Author is "Aragonés Beltrán, José María"

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Article

Ahnert Iglesias, Carolina and Cuervo Gómez, Diana and García Herranz, Nuria and Aragonés Beltrán, José María and Cabellos de Francisco, Oscar Luis and Gallego Díaz, Eduardo F. and Mínguez Torres, Emilio and Lorente Fillol, Alfredo and Piedra, David and Rebollo, Luis and Blanco, Julio (2011). Education and Training of Future Nuclear Engineers Through the use of an Interactive Plant Simulator. "International Journal of Engineering Education", v. 27 (n. 4); pp. 722-732. ISSN 0949-149X.

Lozano Montero, Juan Andrés and Jiménez Escalante, Javier and García Herranz, Nuria and Aragonés Beltrán, José María (2010). Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis.. "Annals of nuclear energy", v. 37 (n. 3); pp. 380-388. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2009.12.00.

Lozano Montero, Juan Andrés and García Herranz, Nuria and Ahnert Iglesias, Carolina and Aragonés Beltrán, José María (2008). The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: Development and performance analysis. "Annals of Nuclear Energy", v. 35 (n. 12); pp. 2365-2374. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2008.07.013.

Aragonés Beltrán, José María and Ahnert Iglesias, Carolina and García Herranz, Nuria (2007). The Analytic Coarse-Mesh Finite Difference Method for Multigroup and Multidimensional Diffusion Calculations. "Nuclear Science and Engineering", v. 157 (n. 1); pp. 1-15. ISSN 0029-5639.

Aragonés Beltrán, José María and Ahnert Iglesias, Carolina and Cabellos de Francisco, Oscar Luis and García Herranz, Nuria and Aragonés Ahnert, Vanessa (2004). Methods and Results for the MSLB NEA Benchmark Using SIMTRAN and RELAP5. "Nuclear Technology", v. 146 (n. 1); pp. 29-40. ISSN 0029-5450.

García Herranz, Nuria and Cabellos de Francisco, Oscar Luis and Aragonés Beltrán, José María and Ahnert Iglesias, Carolina (2003). Analytic Coarse-Mesh Finite-Difference Method Generalized for Heterogeneous Multidimensional Two-Group Diffusion Calculations. "Nuclear Science And Engineering", v. 144 (n. 1); pp. 23-35. ISSN 0029-5639.

Book Section

Aragonés Beltrán, José María and Hill, Barrie Frederick and Kadak, Andrew C. and Shultz, Donald F. and Spitalnik, Jorge (2008). Nuclear Power Feasibility 2007. In: "World Federation of Engineering Organizations, Series on Feasibility of Current Energy Options". 2007 . WFEO Energy Committee & Brazilian Federation of Engineering Associations, Brasil, pp. 1-52. ISBN 978-85-99927-02-1.

Presentation at Congress or Conference

Ochoa Valero, Raquel and García Herranz, Nuria and Aragonés Beltrán, José María (2010). Análisis de la transmutación de Actínidos Minoritarios en un reactor rápido de sodio con modelo de carga homogéneo mediante el código MCNPX-CINDER. In: "36 Reunión Anual de la Sociedad Nuclear Española", 29/10/2010 - 30/10/2010, Santiago de Compostela, España. ISBN ISSN 1137-2885. pp. 10-20.

Jiménez Escalante, Javier and Herrero Carrascosa, José Javier and Lozano Montero, Juan Andrés and Aragonés Beltrán, José María and Cuervo Gómez, Diana and García Herranz, Nuria and Ahnert Iglesias, Carolina (2010). Aplicación del código COBAYA3 al análisis multiescala con acoplamiento neutrónico-termohidráulico en reactores PWR. In: "36 Reunión Anual de la Sociedad Nuclear Española", 27/10/2011 - 29/10/2010, Santiago de Compostela, España.

Ahnert Iglesias, Carolina and Cuervo Gómez, Diana and García Herranz, Nuria and Aragonés Beltrán, José María and Cabellos de Francisco, Oscar Luis and Gallego Díaz, Eduardo F. and Mínguez Torres, Emilio and Lorente Fillol, Alfredo and Piedra, David and Rebollo, Luis and Blanco, Julio (2010). Education and Training of Future Nuclear Engineers Through The use of An Interactive Plant Simulator.. In: "European Nuclear Conference, ENC-2010", 30/05/2010 - 03/06/2010, Barcelona, España.

Cabellos de Francisco, Oscar Luis and Ahnert Iglesias, Carolina and Cuervo Gómez, Diana and García Herranz, Nuria and Gallego Díaz, Eduardo F. and Mínguez Torres, Emilio and Aragonés Beltrán, José María and Lorente Fillol, Alfredo and Piedra, David (2010). Education and Training of Future Nuclear Engineers at DIN: From Advanced Computer Codes to an Interactive Plant Simulator.. In: "International Conference Nuclear Energy for New Europe", 06/09/2010 - 09/09/2010, Portorož, Eslovenia.

Jiménez Escalante, Javier and Herrero Carrascosa, José Javier and Cuervo Gómez, Diana and Aragonés Beltrán, José María (2010). Whole Core Pin-by-Pin Coupled Neutronic-Thermal-hydraulic Steady state and Transient Calculations using COBAYA3 code. In: "17th Pacific Basin Nuclear Conference 2010, PBNC-2010", 24/10/2010 - 30/10/2010, Cancún, México.

Lozano Montero, Juan Andrés and Aragonés Beltrán, José María and García Herranz, Nuria (2009). Development of an Analytic Nodal Diffusion Solver in Multigroups for 3D Reactor Cores with Rectangular or Hexagonal Assemblies.. In: "2nd ENEN Event - International Youth Nuclear Congress ( IYNC ) 2008", 20/09/2008-26/09/2008, Entrelagos, Suiza. ISBN 978-3-9521409-5-6.

Jiménez Escalante, Javier and Herrero Carrascosa, José Javier and Lozano Montero, Juan Andrés and Cuervo Gómez, Diana and García Herranz, Nuria and Ahnert Iglesias, Carolina and Aragonés Beltrán, José María (2009). Descomposición espacial en subdominios para reactores de agua ligera a la escala de la barra de combustible. In: "34º Reunión Anual de la Sociedad Nuclear Española", 29/10/2009-31/10/2009, Murcia, España. ISBN ISSN 1137-2885. pp. 10-12.

Lozano Montero, Juan Andrés and Jiménez Escalante, Javier and García Herranz, Nuria and Aragonés Beltrán, José María (2009). Development and Performance of the ANDES/COBRA-III Coupled System in Hexagonal-Z Geometry. In: "International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009)", May 3-7, 2009, Saratoga Springs, New York. ISBN 978-0-89448-069-0. pp. 1-13.

Lozano Montero, Juan Andrés and Aragonés Beltrán, José María and García Herranz, Nuria (2008). Transient analysis in the 3D nodal kinetics and thermal-hydraulics ANDES/COBRA coupled system. In: "International Conference on the Physics of Reactors “Nuclear Power: A Sustainable Resource”", 14/09/2008-18/09/2008, Interlaken, Suiza. ISBN 978-3-9521409-5-6. pp. 1-8.

Aragonés Beltrán, José María (2008). Basis for Coupled 3-D Neutronics-Thermal-Hydraulics. In: "Seminar on the Transfer of Knowledge Gained through CSNI Activities in the Field of Thermal-hydraulics, THICKET-2008", 05/05/2008-09/05/2008, Pisa,Italia.

Lozano Montero, Juan Andrés and García Herranz, Nuria and Aragonés Beltrán, José María (2008). El código nodal analítico ANDES para difusión en geometría 3D y multi-grupos: Desarrollo y Resultados. In: "34 Reunión Anual de la Sociedad Nuclear Española", 29-31 octubre 2008, Murcia, España. pp. 1-8.

Aragonés Beltrán, José María (2008). Fundamentals of 3-D Neutron Kinetics and Current Status. In: "THICKET-2008: Seminar on the Transfer of Knowledge Gained through CSNI Activities in the Field of Thermal-hydraulics", 05/05/2008-09/05/2008, Pisa,Italia.

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