Browsing by Author "Mas de les Valls Ortiz, Elisabet"
Now showing items 1-20 of 22
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6a Jornada d'Igualtat de la UPC. Projectes emergents 2019
(2019-02-06)
Audiovisual
Open Access -
Análisis de la permeación de tritio en los canales de metal líquido de las envolturas regeneradoras de un reactor de fusión en presencia de burbujas de helio
(2012)
Conference report
Open AccessEn el interior de los canales de metal l quido de las envolturas regeneradoras de un reactor de fusi on, la posibilidad de existencia de burbujas de helio nucleado no es remota. El helio se forma junto al tritio en ... -
An approach to verification and validation of MHD codes for fusion applications
(2015-11)
Article
Open AccessWe propose a new activity on verification and validation (V&V) of MHD codes presently employed by the fusion community as a predictive capability tool for liquid metal cooling applications, such as liquid metal blankets. ... -
Aproximación multiescala a la simulación termohidráulica de reactores de fusión en la Universidad Politécnica de Cataluña
(2014)
Conference report
Restricted access - publisher's policyEl Grupo de Estudios Termohidráulicos (GET) de la UPC posee gran experiencia en estudios de seguridad nuclear mediante códigos de simulación de plantas nucleares. Desde 1987, el grupo ha colaborado con las CN de Ascó y ... -
Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module
(2016-09-01)
Article
Open AccessWithin the framework of EUROfusion Program, the Dual Coolant Lithium Lead (DCLL) is one of the four EU breeder blanket concepts that are being investigated as candidates for DEMO. DCLL uses PbLi as the main coolant, tritium ... -
Desarrollo e implementación de un modelo de permeación de tritio en presencia de burbujas de helio para envolturas tritigénicas de metal líquido
(2013)
Conference report
Restricted access - publisher's policyEn los canales de metal líquido (ML) de las envolturas regeneradoras de un reactor de fusión la posibilidad de formación de burbujas de helio no es remota. La presencia de burbujas adheridas a la pared de los canales de ... -
Development of a simulation tool for MHD flows under nuclear fusion conditions
(Universitat Politècnica de Catalunya, 2011-12-01)
Doctoral thesis
Open AccessIn Nuclear Fusion Technology, MHD flows can be encountered in liquid metal (LM) breeding blankets, the part of a fusion reactor where tritium, one of the fusion fuels, is to be produced. There are several types of LM ... -
Estudio paramétrico de un diseñoo conceptual de envoltura regeneradora He/LiPb de doble refrigerante para DEMO
(2011)
Conference lecture
Restricted access - publisher's policyEl programa Espa~nol de Tecnolog a de Envolturas Regeneradoras TECNO FUS est a estudiando la viabilidad tecnol ogica de un reactor con especi caciones DEMO y envolturas regeneradoras tipo Doble Refrigerante He/Pb15.7Li. ... -
Flow analysis in the HCLL-TBM ITER channels including MHD and heat transfer
(2010)
Conference lecture
Open AccessOne of the key components regarding heat transfer and tritium inventories in deuterium-tritium nuclear fusion reactors is the (tritium) Breeding Blanket, called Test Blanket Module or TBM in ITER experiment. Several ... -
Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules
(2011)
Article
Restricted access - publisher's policyTritium self-sufficiency requirement of future DT fusion reactors involves large helium production rates in the breeding blankets; this might impact on the conceptual design of diverse fusion power reactor units, such ... -
Mathematical models for tritium permeation analysis in liquid metal flows with helium bubbles
(2014-10-01)
Article
Restricted access - publisher's policyIn LIBRETTO-2 test, evidence was obtained that helium bubbles nucleated and grew in the neutron irradiated PbLi probes. If such phenomenon occurs inside liquid metal (LM) breeding blanket channels, the study of its effect ... -
MHD issues related to the use of Lithium Lead eutectic as breeder material for blankets of fusion power plants
(2015-04-01)
Article
Restricted access - publisher's policyThe European Community is committed to the development of a DEMOnstration fusion power plant whose operation could start as soon as 2050. The blanket is one of the most critical components in a fusion reactor; three of the ... -
MHD para fusión: parámetros puente entre CFD y códigos de sistema
(2012)
Conference lecture
Restricted access - publisher's policy -
Modelado de un ciclo de potencia de CO2 supercrítico para reactores de fusión utilizando RELAP5-3D
(2013)
Conference report
Restricted access - publisher's policyEn el marco del programa español de Tecnología de Fusión TECNO_FUS se ha avanzado en la definición de sistemas para DEMO, entre ellos las unidades reproductoras de tritio y el ciclo de potencia. Para las primeras, se ha ... -
Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5-3D
(2014-04-01)
Article
Restricted access - publisher's policyA supercritical recompression CO2 power cycle has been simulated using the system code RELAP5-3D. This code is being developed by INL and has traditionally been used in the simulation of operational and accidental transients ... -
Numerical analysis of MHD-thermofluid flows considering sandwich structures as applied to liquid breeding blankets for fusion technology
(2011)
Conference report
Restricted access - publisher's policyLead lithium flowing inside breeding blanket’s channels in a fusion reactor is subject to a Hartmann number of 104 and a Grashof number 10912. Since under such conditions buoyancy can be of the same order of magnitude ... -
Numeric implementation of a nucleation, growth and transport model for helium bubbles in lead–lithium HCLL breeding blanket channels: Theory and code development
(2011)
Article
Restricted access - publisher's policyLarge helium (He) production rates in liquid metal breeding blankets of a DT fusion reactor might have a significant influence in the system design. Low He solubility together with high local concentrations may create the ... -
RELAP/SCDAPSIM/MOD4.0 modification for transient accident scenario of test blanket modules involving helium flows into heavy liquid metal
(2015)
Conference lecture
Restricted access - publisher's policyThe Institute for Plasma Research (IPR), India, is currently involved in the design and development of its Test Blanket Module (TBM) for testing in ITER (International Thermo nuclear Experimental Reactor). The Indian TBM ... -
Simulación numérica de fenómenos de convección natural. Aplicación a un sistema solar termosifón para la obtención de agua caliente sanitaria
(Universitat Politècnica de Catalunya, 2004)
Master thesis (pre-Bologna period)
Open Access
