Exploració per tema "Combustibles nuclears"
Ara es mostren els items 1-18 de 18
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Analysis of the evolution of the actinides composition and their reaction rates in GFR600
(Universitat Politècnica de Catalunya / Budapest University of Technology and Economics, 2009)
Projecte/Treball Final de Carrera
Accés restringit per decisió de l'autor
Realitzat a/amb: Budapesti Műszaki és Gazdaságtudományi EgyetemThe present report explains the work done and the results achieved in the framework explained at the Introduction section. This work is the author’s Master Thesis that concludes the Industrial Engineering university career ... -
Characterization of eutectic oxides and relationship between microstructure and process
(Universitat Politècnica de Catalunya, 2014-09)
Projecte Final de Màster Oficial
Accés restringit per acord de confidencialitat
Realitzat a/amb: École nationale supérieure de physique, électronique et matériaux -
Construction and qualification of a micro-tensile testing machine for lower scale digital image correlation applied to Zirconium alloys
(Universitat Politècnica de Catalunya, 2014-06)
Projecte/Treball Final de Carrera
Accés obertThe aim of this project is the construction, programming and operation of a thermo-mechanical testing machine for the study of the mechanical properties of nuclear fuel cladding material. The strain information is estimated ... -
Determinación de parámetros neutrónicos de los elementos de combustible de un PWR para uso en códigos acoplados NKTH y códigos TH con cinética puntual
(Universitat Politècnica de Catalunya, 2010-04)
Projecte/Treball Final de Carrera
Accés obertEn esta memoria se explica brevemente el estado del arte del cálculo del transporte de neutrones, los fundamentos de la teoría de difusión así como las hipótesis y recursos que implementan los diferentes códigos informáticos ... -
Development of a research plan for electrochemical studies of gadolinium doped uranium oxide
(Universitat Politècnica de Catalunya, 2020-07-13)
Treball Final de Grau
Accés obertActualment, el combustible nuclear és una de les fonts d’energia més emprades del planeta. En la majoria de casos, l’òxid d’urani (UO2) constitueix majoritàriament el combustible degut a la seva alta eficiència i les ... -
Dynamic leaching studies of 48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions
(2013-03)
Article
Accés restringit per política de l'editorialThe leaching of a high-burn-up spent nuclear fuel (48 MWd/KgU) has been studied in a carbonate-containing solution and under oxic conditions using a Continuously Stirred Tank Flow-Through Reactor (CSTR). Two samples of the ... -
Estudi de vulnerabilitat, recursos i establiment del Protocol d'Actuació en el Transport de Combustible Nuclear a Ascó II
(Universitat Politècnica de Catalunya, 2011-11)
Projecte/Treball Final de Carrera
Accés obertEn aquest projecte s’estableix un procediment d’actuació davant possibles accidents de caràcter industrial, focalitzat en el transport de mercaderies perilloses, concretament combustible nuclear format per Òxids d’Urani ... -
Estudio del primer ciclo de quemado del combustible del reactor nuclear avanzado EPR
(Universitat Politècnica de Catalunya, 2010-09)
Projecte/Treball Final de Carrera
Accés obertEl presente proyecto final de carrera se enmarca en el convenio de colaboración entre el Consejo de Seguridad Nuclear (CSN) y la Universitat Politècnica de Catalunya (UPC) para la realización de proyectos en el ámbito ... -
Influence of the interpellet space to the Instant Release Fraction determination of a commercial UO2 Boiling Water Reactor Spent Nuclear Fuel
(Elsevier, 2018-02)
Article
Accés obertThe contact of the coolant with the fuel pin during irradiation produces a gradient of temperature in the fuel pellet that segregates the radionuclides (RN) depending on its volatility and reactivity. This segregation ... -
Material requirements for a thorium based nuclear fuel
(Universitat Politècnica de Catalunya / Aalto University School of Science and Technology, 2010)
Projecte/Treball Final de Carrera
Accés obertThe increase in the energy consumption and the expected growth in the nuclear capacity make it necessary to look for alternative fuels to replace uranium. The fuel chosen, which was also considered in the early stages ... -
Molybdenum release from high burnup spent nuclear fuel at alkaline and hyperalkaline pH
(Elsevier, 2023-01-01)
Article
Accés obertThis work presents experimental data and modelling of the release of Mo from high-burnup spent nuclear fuel (63 MWd/kgU) at two different pH values, 8.4 and 13.2 in air. The release of Mo from SF to the solution is around ... -
Oxidation by H2O(g) in the presence of H2(g) of UO2 doped with Pd nanoparticles
(2018-09-28)
Article
Accés obertThis work studies the influence of epsilon particles and metallic precipitates, simulated through the deposition of Pd nanoparticles on non-irradiated UO2, on the oxidation of the spent nuclear fuel (SNF). The presence of ... -
Perfecting the use of hybrid models in scaling analysis
(2019-12-01)
Article
Accés obertDifferent methodologies devoted to qualify Nuclear Power Plant (NPP) system-code nodalizations rely on Kv-scaled calculations as an essential tool for their purpose. In the framework of Power-To-Volume strategy, a Kv-scaled ... -
Production of Mixed U–Zr Nitride Nuclear Fuel Powders from Metallic U–Zr Alloys
(Universitat Politècnica de Catalunya / Kungliga Tecniska Högskolan, 2010)
Projecte/Treball Final de Carrera
Accés obertThe main objective of this master thesis was assessing and evaluating the production of mixed U-Zr nitride fuel powders directly from metallic U-Zr binary alloys, instead of using separate nitride powders. Another secondary ... -
Safety aspects of Ceramic Fully Encapsulated fuel for Light Water Reactors
(Universitat Politècnica de Catalunya / Kungliga Tekniska Högskolan, 2011)
Projecte/Treball Final de Carrera
Accés obertJapan’s nuclear disaster has highlighted important inherent weaknesses regarding to the nuclear fuel behavior after shutdown in Light Water Reactors. The low thermal conductivity and the low fission products retention ... -
Simulation of CabriI Loss-Offlow Experiments With The Trace/Fred Codes
(Universitat Politècnica de Catalunya / Eidegenössische Technische Hochschule Zürich, 2009)
Projecte/Treball Final de Carrera
Accés restringit per decisió de l'autorThis thesis, “Simulation of CABRI loss-of-flow experiments with the TRACE/FRED codes”, is a result of cooperation with IRSN (France), who transferred to PSI the CABRI facility specification and test data. The thesis has ... -
Soluciones con programación lineal entera mixta para el almacenamiento monoetápico del combustible nuclear gastado en cápsulas MPC-32 en la central nuclear Ascó 1
(2020-05-20)
Report de recerca
Accés obertSe presenta en detalle siete soluciones óptimas para la instancia de datos Ascó#01_06 relacionada con la central nuclear Ascó-1 ubicada a 160 km de Barcelona. El procedimiento utilizado para hallar tales soluciones se ... -
Study of a PWR fuel assembly model in 2D and 3D during code irradiation using the inventory calculation system KENOREST
(Universitat Politècnica de Catalunya / Technishe Universität München, 2009)
Projecte/Treball Final de Carrera
Accés restringit per decisió de l'autorAt the present time, 2D depletion codes are the state of the art. KENOREST has been specially developed by the company Gesellschaft für Anlagen- un Reaktorsicherheit as a 2D and 3D depletion code. Although 3D depletion ...