Browsing by Subject "Nuclear reactors -- Safety measures"
Now showing items 1-7 of 7
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Contribution to safety analyses of DEMO HCPB using AINA code
(2018-11-27)
Article
Open AccessThe motivation of the current work, framed under the safety EUROfusion activities to develop DEMO, is to present the conclusions drawn from our contribution to the safety studies of the HCPB DEMO carried out by the team ... -
Desarrollo de la infraestructura para la validación del código de seguridad AINA
(Universitat Politècnica de Catalunya, 2015-06)
Bachelor thesis
Restricted access - author's decisionEn el presente informe se realiza una revisión del informe “Review of Loss of Plasma Control Transient in ITER” realizado por Fusion Energy Engineering Laboratory (FEEL-UPC) en Agosto de 2007 mediante el código de seguridad ... -
Estudio de seguridad del acoplamiento de un reactor de alta temperatura (VHTR) con una planta de producción de hidrógeno, análisis de los accidentes relevantes asociados
(Universitat Politècnica de Catalunya, 2008-10)
Master thesis (pre-Bologna period)
Open AccessUn estudio preliminar de seguridad dedicado al acoplamiento de un reactor nuclear de muy alta temperatura (Very High Temperature Reactor) con una planta de producción de hidrógeno (HYdrogen Production Plant) según el proceso ... -
Multi-unit Considerations of Seaborg's Compact Molten Salt Reactor
(Universitat Politècnica de Catalunya, 2021-04-22)
Master thesis
Restricted access - confidentiality agreement
Covenantee: École nationale supérieure de techniques avancées / Seaborg Technologies -
Passive plasma termination for beryllium evaporation in LOCA transients in ITER with AINA 3.0 code
(Universitat Politècnica de Catalunya, 2014-10)
Master thesis (pre-Bologna period)
Restricted access - author's decisionThe present report is a study of loss of coolant accidents transients in ITER. A whole bunch of analyses has been done with AINA 3.0, the safety code developed by Fusion Energy Engineering Laboratory (FEEL-UPC) on the basis ... -
Risk Analysis of an interfacing system LOCA in a generic Westinghouse PWR
(Universitat Politècnica de Catalunya / École supérieure d'électricité, 2014)
Master thesis
Open AccessThis project has been developed during my internship in the field of Probabilistic Safety Assessment (PSA) in the offices of Westinghouse. These are in the enclosure of Vandellòs’ Nuclear Plant in Hospitalet de l'Infant. The ... -
Safety aspects of Ceramic Fully Encapsulated fuel for Light Water Reactors
(Universitat Politècnica de Catalunya / Kungliga Tekniska Högskolan, 2011)
Master thesis (pre-Bologna period)
Open AccessJapan’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 ...
