Recursos de colección

Archivo Digital UPM (107.543 recursos)

This is an institutional repository providing access to the research output of the institution. Primarily contains thesis.

Materia = Energía Nuclear

Mostrando recursos 1 - 20 de 213

  1. Non-Maxwellian electron distributions in time-dependent simulations of low-Z materials illuminated by a high-intensity X-ray laser

    García de La Varga, Alberto; Velarde Mayol, Pedro; Gaufridy, François de; Portillo Garcia, David; Cotelo Ferreiro, Manuel; Barbas, A.; González Fernández, Agustín; Zeitoun, Philippe
    The interaction of high intensity X-ray lasers with matter is modeled. A collisional-radiative timedependent module is implemented to study radiation transport in matter from ultrashort and ultraintense X-ray bursts. Inverse bremsstrahlung absorption by free electrons, electron conduction or hydrodynamic effects are not considered. The collisional-radiative system is coupled with the electron distribution evolution treated with a Fokker-Planck approach with additional inelastic terms. The model includes spontaneous emission, resonant photoabsorption, collisional excitation and de-excitation, radiative recombination, photoionization, collisional ionization, three-body recombination, autoionization and dielectronic capture. It is found that for high densities, but still below solid, collisions play an important role...

  2. Methodologies for an improved prediction of the isotopic content in high burnup samples. Application to Vandellos-II reactor core

    Martínez, J.S.; Cabellos de Francisco, Oscar Luis; Diez de la Obra, Carlos Javier
    Fuel cycles are designed with the aim of obtaining the highest amount of energy possible. Since higher burnup values are reached, it is necessary to improve our disposal designs, traditionally based on the conservative assumption that they contain fresh fuel. The criticality calculations involved must consider burnup by making the most of the experimental and computational capabilities developed, respectively, to measure and predict the isotopic content of the spent nuclear fuel. These high burnup scenarios encourage a review of the computational tools to find out possible weaknesses in the nuclear data libraries, in the methodologies applied and their applicability range....

  3. Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1

    Diez de la Obra, Carlos Javier; Stankovskiy, Alexey; Malambu, E.; Zerovnik, Gasper; Schillebeeckx, Peter; Van den Eynde, Gert; Heyse, Jan; Cabellos de Francisco, Oscar Luis
    A review of the experimental data for natC(n,c) and 12C(n,c) was made to identify the origin of the natC capture cross sections included in evaluated data libraries and to clarify differences observed in neutronic calculations for graphite moderated reactors using different libraries. The performance of the JEFF-3.1.2 and ENDF/B-VII.1 libraries was verified by comparing results of criticality calculations with experimental results obtained for the BR1 reactor. This reactor is an air-cooled reactor with graphite as moderator and is located at the Belgian Nuclear Research Centre SCK-CEN in Mol (Belgium). The results of this study confirm conclusions drawn from neutronic calculations...

  4. Preliminary approach to neutron instrument selecction at ESSB-Bilbao based on experience at ISIS molecular spectroscopy group

    Vicente Bueno, Jesús Pedro de
    Collaborative efforts between the Neutronics and Target Design Group at the Instituto de Fusión Nuclear and the Molecular Spectroscopy Group at the ISIS Pulsed Neutron and Muon Source date back to 2012 in the context of the ESS-Bilbao project. The rationale for these joint activities was twofold, namely: to assess the realm of applicability of the low-energy neutron source proposed by ESS-Bilbao - for details; and to explore instrument capabilities for pulsed-neutron techniques in the range 0.05-3 ms, a time range where ESS-Bilbao and ISIS could offer a significant degree of synergy and complementarity. As part of this collaboration, J.P....

  5. Processing of the JEFF-3.1.2 Cross Section Library into various formats (ACE, PENDF, GENDF, MATXSR and BOXER) for testing purposes

    Cabellos de Francisco, Oscar Luis
    1. Objectives and planning 1.1 Processing JEFF-3.1.2 in ACE format 1.2 Processing JEFF-3.1.2 to JANIS and BOXER format 1.3 Changes in NJOY99.364 1.4 Updates in JEFF-3.1.2 1.5 Processing TENDL-2011

  6. Application of a dynamic event tree methodolgy to steam generator tube rupture sequences

    Queral Salazar, José Cesar; Rebollo, M.J.; Jimenez Varas, Gonzalo; Ibañez, L.; Gil, Jesús; Fernández, Iván; Gómez Magán, J.J.; Marrao, Hugo; Sánchez Perea, Miguel; Hortal Reymundo, Javier; Izquierdo Rocha, José María; Meléndez Asensio, Enrique
    The Integrated Safety Assessment (ISA) methodology, developed by the Spanish Nuclear Safety Council (CSN), has been applied to a thermo-hydraulical analysis of a Westinghouse 3-loop PWR plant by means of the dynamic event trees (DET) for Steam Generator Tube Rupture (SGTR) sequences. The ISA methodology allows obtaining the SGTR Dynamic Event Tree taking into account the operator actuation times. Simulations are performed with SCAIS (Simulation Code system for Integrated Safety Assessment), which includes a dynamic coupling with MAAP thermal hydraulic code. The results show the capability of the ISA methodology and SCAIS platform to obtain the DET of complex sequences.

  7. Building the qualification and a skill development program within the ENEN-III European Project

    Mínguez Torres, Emilio; Jimenez Varas, Gonzalo; González, M.
    The ENEN III project covers the structuring, organization, coordination and implementation of training schemes in cooperation with local, national and international training organizations, to provide training to professionals active in nuclear organizations or their contractors and sub-contractors. The training schemes provide a portfolio of courses, training sessions, seminars, and workshops for continuous learning for upgrading knowledge and developing skills. The training schemes allow individuals to acquire qualifications and skills, as required by the specific positions in the nuclear sector which will be documented in a training passport. The essence of such passport is to be recognized within the EU by...

  8. Simulación del accidente de SGTR en un PWR-W con TRACE para distintas metodologías de análisis determinista de seguridad

    Jimenez Varas, Gonzalo; Queral Salazar, José Cesar; Rebollo, M.J.; Martínez-Murillo Méndez, Juan Carlos
    A Steam Generator Tube Rupture (SGTR) in a Pressurized Water Reactor (PWR) can lead to an atmospheric release bypassing the containment via the secondary system and exiting though the Pressurized Operating Relief Valves of the affected Steam Generator. That is why SGTR historically have been treated in a special way in the different Deterministic Safety Analysis (DSA), focusing on the radioactive release more than the possibility of core damage, as it is done in the other Loss of Coolant Accidents(LOCAs).

  9. Mejoras en el sistema MOIRA para su aplicación a los emplazamientos nucleares fluviales españoles

    Gallego Díaz, Eduardo F.; Iglesias Ferrer, Rafael; Dvorzhak, Alla; Hofman, Dmitry
    Entre las posibles secuelas de un accidente nuclear hay que contar con la contaminación radiactiva a medio y largo plazo de los sistemas acuáticos de agua dulce. Frente a ese problema, es fundamental disponer de una evaluación realista del impacto radiológico, ecológico, social y económico de las posibles estrategias de gestión, para poder adoptar las decisiones más convenientes de forma racional. MOIRA es un sistema de ayuda a la decisión desarrollado en el curso de los Programas Marco Europeos con participación de la UPM, que ha sido mejorado y adaptado a los emplazamientos nucleares españoles en los últimos años en...

  10. Plasmonic nanoparticles for the protection of the final optics in inertial confinement fusion facilities: capabilities and limitations

    Peña Rodriguez, Ovidio Y.
    Final lenses in laser fusion plants. Challenges for the protection of the final lenses. Plasmonic nanoparticles. Radiation resistance

  11. Nanostructured tungsten as a first wall material for the future nuclear fusion reactors

    Gordillo Garcia, Nuria; Gonzalez Arrabal, Raquel; Rivera de Mena, Antonio; Fernández, I.; Briones Fernández-Pola, Fernando; Rio, David del; Gómez, C.; Pastor, Jose Ygnacio; Tejado Garrido, Elena Maria; Panizo-Laiz, M.; Perlado Martin, Jose Manuel
    The lack of materials able to withstand the severe radiation conditions (high thermal loads and atomistic damage) expected in fusion reactors is the actual bottle neck for fusion to become a reality. The main requisite for plasma facing materials (PFM) is to have excellent structural stability since severe cracking or mass loss would hamper their protection role which turns out to be unacceptable. Additional practical requirements for plasma facing materials are among others: (i) high thermal shock resistance, (ii) high thermal conductivity (iii) high melting point (iv) low physical and chemical sputtering, and (v) low tritium retention.

  12. Nanocrystals in the manufacture of target for inertial confinement fusion

    Guerrero, Carlo; Perlado Martin, Jose Manuel; Cuesta Lopez, Santiago
    Systems inertial confinement fusion (ICF) need of a manufacturing process targets very accurate and efficient (Fig. A). Due to the frequency needed for energy production techniques are necessary to achieve high repetition rates, however it is also necessary to increase or maintain the quality and efficiency of these targets. In order to observe more resolution possible problems in the target manufacture (B), we propose the following theoretical methodology, by means of which analyze different phenomena present in the conditions which are fabrication and handled deuterium tritium target spheres (DT ice). Recent experiments show that addition of instabilities caused by the...

  13. El sistema JRODOS: una herramienta moderna y eficaz para la gestión y preparación de emergencias nucleares y radiológicas y la rehabilitación. Implementación en España.

    Montero Prieto, Milagros; Dvorzhak, Alla; Gallego Díaz, Eduardo F.
    En los últimos años se ha producido un significativo avance en el área de la gestión de las emergencias nucleares y radiológicas y la rehabilitación. Proyectos de alcance europeo como EURANOS han contribuido a mejorar los procesos de gobernanza participativa iniciados durante los anteriores Programas Marco Europeos y el desarrollo de técnicas y metodologías en todos los niveles operativos en materia nuclear y radiológica. El sistema de ayuda a la decisión (SAD) RODOS es uno de los productos desarrollados durante este periodo y que ha ido siendo mejorado hasta convertirse en un sistema de uso operacional ampliamente difundido y asumido...

  14. Caracterización y empleo de "conos de sombra" en un laboratorio para calibración neutrónica

    Gallego Díaz, Eduardo F.; Valle Díez, Aurora del; Lorente Fillol, Alfredo; Vega-Carrillo, Héctor René; Méndez Villafañe, Roberto; Ibáñez Fernández, Javier
    En laboratorios de calibración neutrónica, si las diferencias entre los espectros neutrónicos “en el lugar de trabajo” y los utilizados en la instalación de calibración son muy acusadas, resulta muy complicado obtener factores de normalización adecuados, siendo conveniente tratar de producir campos neutrónicos “realistas”, es decir, cuyo espectro energético sea similar al existente en el lugar de trabajo, lo que permitiría la calibración directa de los instrumentos dosimétricos. Uno de los métodos utilizados, es el método de los “conos de sombra”. En este trabajo se presentan el diseño, caracterización y empleo de los conos de sombra del Laboratorio de medidas...

  15. UPM Activities on the STLs processing (Task 6.2) and the generation of DPA cross section library up to 150 MeV (Task 4.1)

    Cabellos de Francisco, Oscar Luis; Castro González, Emilio
    Generation of a complete damage energy and dpa cross section library up to 150 MeVbased on JEFF- 3.1.1 and suitable approximations (UPM) Postprocessing of photonuclear libraries (by CCFE) and thermal scattering  tables (by UPM) at the backend of the calculational system (CCFE/UPM)

  16. Conceptual design of liquid lithium laboratory in the TECHNOFUSION project

    González del Moral, Octavio; García, A.; Casal, N.; Abánades Velasco, Alberto; Ibarra, A., A.; Perlado Martin, Jose Manuel
    The Technofusion project involves the construction of a relevant set of scientific technical facilities in Madrid, providing new tools to fusion energy community.

  17. Quantum molecular dynamics and ab initio studies of the crystal structure of hydrogen and deuterium

    Guerrero, Carlo; Perlado Martin, Jose Manuel; Cuesta Lopez, Santiago
    Hydrogen isotopes play a critical role both in inertial and magnetic confinemen Nuclear Fusion. Since the preferent fuel needed for this technology is a mixture of deuterium and tritium. The study of these isotopes particularly at very low temperatures carries a technological interest in other applications. The present line promotes a deep study on the structural configuration that hydrogen and deuterium adopt at cryogenic temperatures and at high pressures. Typical conditions occurring in present Inertial Fusion target designs. Our approach is aims to determine the crystal structure characteristics, phase transitions and other parameters strongly correlated to variations of temperature and pressure.

  18. Ionoluminescence on α-quartz: mechanisms and modeling

    Peña Rodriguez, Ovidio Y.; Jimenez Rey, D.; Olivares, J.; Rivera de Mena, Antonio; Agullo Lopez, Fernando
    Ionoluminescence of α - quartz exhibits two dominant emission bands peaking at 1.9 eV. (NBOHCs) and 2.7 eV (STEs. The evolution of the red emission yield does not show a correlation with the concentrations of neither the NBOHC nor with that of other color centers. The blue emission yield closely follows the amorphization kinetics independently measured by RBS/C spectrometry. A simple theoretical model has been proposed; it assumes that the formation and recombination of STEs are the primary event and both, the light emissions and the lattice structural damage are a consequence this phenomenon. The model leads to several simple mathematical equations that...

  19. Estudio de la anisotropía de una fuente de Am-Be de 111 GBq

    Méndez Villafañe, Roberto; Gallego Díaz, Eduardo F.; Lorente Fillol, Alfredo; Ibáñez, Sviatovslav; Guerrero Araque, Jorge Enrique
    Se ha estudiado la anisotropía de una fuente de Am-Be de 111 GBq (3Ci) mediante el uso de un pequeño motor que permite girar paso a paso la fuente situada en su posición de irradiación habitual. Las medidas se han realizado con un contador proporcional de 3He alojado en el interior de una esfera moderadora de 8” correspondiente a un sistema de espectrometría de esferas Bonner. Se reportan los resultados obtenidos y el factor de anisotropía determinado para esta fuente.

  20. Descontaminación y recuperación de áreas contaminadas

    Gallego Díaz, Eduardo F.
    Tras el accidente de Fukushima, se han puesto en marcha una serie de actividades de caracterización y descontaminación de las zonas contaminadas alrededor de la central, destinadas a facilitar su habitabilidad. A partir de la experiencia de Japón, que el ponente conoce de cerca como miembro de la red europea NERIS-TP y tras participar en una reciente misión a Fukushima, en este curso se abordaron las técnicas más actuales que se utilizan para diseñar y proponer estrategias de cara a la recuperación de grades superficies contaminadas.

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