Browsing by Author "Mas de les Valls Ortiz, Elisabet"
Now showing items 1-20 of 56
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6a Jornada d'Igualtat de la UPC. Projectes emergents 2019
(2019-02-06)
Audiovisual
Open Access -
A Formal Verification and Validation of a Low Magnetic Reynolds Number MHD Code for Fusion Applications
(Institute of Electrical and Electronics Engineers (IEEE), 2022-01-01)
Article
Open AccessAs the nuclear fusion research advances, resear-chers and engineers focus more on the design of the required systems that complement the nuclear fusion reaction in the plasma of a Tokamak. Some proposals for breeding ... -
Absenteeism in maritime education: insights, challenges, and innovative solutions
(Massachusetts Maritime Academy, 2024)
Conference report
Open AccessStudents’ attendance at classes is a measure that reflects students’ enthusiasm for the course and their status in the university. University-level absenteeism is influenced by various factors, ranging from academic ... -
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. ... -
Analysis of flow channel insert deformations influence on the liquid metal flow in DCLL blanket channels
(2020-08-01)
Article
Open AccessThe dual coolant lithium lead (DCLL) is a candidate to be an effective breeding blanket (BB) concept for nuclear fusion technologies. One critical point of this design is the magnetohydrodynamic (MHD) effects involving ... -
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 ... -
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 ... -
Apuntes de termotecnia
(Universitat Politècnica de Catalunya, 2024-11)
Lecture notes
Open Access -
Col·lecció d'exàmens de convecció/bescanviadors
(Universitat Politècnica de Catalunya, 2024-04)
Problem statement, exercise
Open Access -
Col·lecció d'exàmens de mètodes numèrics: enunciat-resultat-resolució
(Universitat Politècnica de Catalunya, 2024-04)
Problem statement, exercise
Open Access -
Col·lecció d’Exàmens de Radiació
(Universitat Politècnica de Catalunya, 2024-05)
Problem statement, exercise
Open Access -
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 ... -
Development of flow regime maps for lead lithium eutectic–helium flows
(2020-09-01)
Article
Open Accessnstitute for Plasma Research (IPR), Gandhinagar (India) is currently involved in the design and development of its Lead-Lithium Ceramic Breeder (LLCB) module for testing in the International Thermo-nuclear Experimental ... -
Estrategias de monitorización de la electrólisis de hidrógeno en electrolizadores PEM
(Publicacions de la Universitat Jaume I, 2023)
Conference lecture
Open Access -
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 ... -
Formularis
(Universitat Politècnica de Catalunya, 2024-05)
Lecture notes
Open Access
