1,721,262 research outputs found
Progetto FAST (Fusion Advanced Studies Torus) proposto dall'Associazione Euratom–ENEA per realizzare un tokamak satellite di ITER da costruire in Europa. http://www.sede.enea.it/attivita_ricerca/energia/fusione_nucleare/Progetto-Fast.html
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Project Leader of WPDTT2 (Definition and design of the Divertor Tokamak Test facility)
No full textEFDA published “Fusion Electricity – A roadmap to the realisation of fusion energy” 0 in November 2012 that sets out a strategic vision to demonstrate the generation of electrical power by a Demonstration Fusion Power Plant (DEMO) by 2050. The roadmap elaborates 8 strategic missions to tackle the main challenges in achieving this overall goal. The need for the WPDTT2 (Definition and Design of the Divertor Tokamak Test Facility) Project is derived from the following statement within the Roadmap:
Mission 2: “Heat-exhaust systems”.
WPDTT2: Definition and design of the Divertor Tokamak Test facility
Management:
Work Package Project Leader
Description:
This work package comprises subprojects which deal with the definition and the conceptual design of Divertor Test Tokamak. The conceptual design will be started after review of the remaining gaps and the possible solutions taking into account the results of the work packages WPPFC and WPDTT1 and the recommendations of the expert panel initiated by the EFDA SC in 2013. It must provide enough positive evidence that the investigated solutions could be integrated in a DEMO device in case the conventional divertor solution does not yield the necessary capabilities for power exhaust. The eventual DTT conceptual design activity should be performed in close coordination with the DEMO design integration project (WPPMI).
Key deliverables:
Headline 2.4: Investigate alternative power exhaust solutions for DEMO
- Definition of DTT technical requirements (2015)
- DTT conceptual design (new machine or upgrade of existing device) (2017, depending on outcome of the review
PRIN 201-2011 Effetti tridimensionali, non lineari e multiphysics nella modellistica e nel controllo dei dispositivi per la fusione termonucleare controllata
No full textL'unità di Napoli DIEL fornirà il proprio contributo a ciascuna delle quattro linee di attività (Work Packages) come illustrato nel seguito.
WP1. Halo currents in strutture conduttrici tridimensionali
1.1 Modellistica tridimensionale delle strutture
(modelli dinamici e adinamici, completi e ridotti)
1.2 Modellistica di correnti di alone
(configurazioni 2D assialsimmetriche e 3D MHD consistenti; equilibri 2D assialsimmetrici evolutivi; modelli linearizzati di RWMs con componenti n>0)
1.3 Sviluppo di tecniche di parallelizzazione/velocizzazione e utilizzo di architetture GPU
(tecniche basate sulla riduzione del modello)
1.4 Confronto tra codici numerici con diverse assunzioni
(confronto modelli dinamici/adinamici e completi/ridotti)
1.5 Applicazioni a dispositivi esistenti o in fase di progetto
(principalmente applicazioni a ITER e JET)
WP2. Modellistica tridimensionale nonlineare dell'evoluzione delle disruptions
2.1 Sviluppo di modelli nonlineari di plasma
(modelli evolutivi nonlineari MHD 2D assialsimmetrici)
2.2 Accoppiamento con strutture conduttrici tridimensionali
(accoppiamento fra plasmi 2D assialsimmetrici e strutture 3D)
2.3 Sviluppo di tecniche di parallelizzazione/velocizzazione e utilizzo di architetture GPU
(tecniche basate sulla riduzione del modello)
WP3. Modellistica e controllo multimodale delle instabilità MHD
3.1 Messa a punto di modelli mono- e multimodali di instabilità MHD
(modello dello spostamento del plasma)
3.2 Accoppiamento con strutture conduttrici tridimensionali
(ottimizzazione della formulazione integrale 3D per le correnti indotte ai fini dell'accoppiamento)
3.3 Sviluppo di tecniche di parallelizzazione/velocizzazione e utilizzo di architetture GPU
(tecniche basate sulla riduzione del modello)
3.8 Applicazioni a dispositivi esistenti o in fase di progetto
(applicazioni su ITER, MAST, JET, FTU e/o RFX)
WP4. Effetti tridimensionali sull'identificazione di plasma
4.1 Modellistica tridimensionale delle strutture e dei magneti
(modelli basati su formulazioni integrali; formulazioni approssimate basate sulle sorgenti equivalenti)
4.2 Studio approssimato di equilibri tridimensionali
(formulazioni basate sulle sorgenti equivalenti)
4.3 Sviluppo di tecniche di identificazione tridimensionale
(formulazioni basate sulle sorgenti equivalenti; calcolo della distanza plasma-parete; ricostruzione delle halo currents)
4.5 Applicazioni a dispositivi esistenti o in fase di progetto
(applicazioni su ITER, FAST, MAST, JET, FTU e/o RFX)
Testo inglese
The Research Unit of Napoli-DIEL will work on the following tasks:
WP1. Halo currents in three-dimensional conducting structures
1.1 Three-dimensional modelling of the structures
(full eddy current models and simplified approaches based on the resistive approximation or the model reduction)
1.2 Halo Currents Modelling
(2D Axisymmetric and 3D MHD consistent configurations; 2D axisymmetric evolution; linearized models of resistive wall modes with n>0 components)
1.3 Development of techniques for parallelization/acceleration and use of GPU architectures
(Techniques based on model reduction)
1.4 Comparison between numerical codes based on different assumptions
(techniques based on simplifying assumptions vs full eddy current models)
1.5 Applications to existing devices and tokamaks under design
(Mainly applications to ITER and JET)
WP2. Three-dimensional nonlinear modelling of disruptions
2.1 Development of nonlinear models
(2D axisymmetric nonlinear MHD models)
2.2 Coupling with three-dimensional conducting structures
(Coupling between 2D axisymmetric plasmas and 3D structures)
2.3 Development of techniques for parallelization/acceleration and use of GPU architectures
(Techniques based on model reduction)
WP3. Multimodal modelling and control of MHD instabilities
3.1 Development of models of single and multimode MHD instabilities
(Model of plasma boundary displacement)
3.2 Coupling with three-dimensional conducting structures
(Optimization of the integral 3D formulation for eddy current for coupling purposes)
3.3 Development of techniques for parallelization/acceleration and use of GPU architectures
(Techniques based on model reduction)
3.8 Applications to existing devices and tokamaks under design
(Applications on ITER, MAST, JET, FTU and / or RFX)
WP4. Three-dimensional effects on plasma identification
4.1 Three-dimensional modelling of structures and magnets
(Models based on integral formulations; approximate formulations based on equivalent sources)
4.2 Approximate study of three-dimensional equilibria
(rigid motion and/or expansion contraction of 2D axisymmetric plasmas; formulations based on equivalent sources)
4.3 Development of techniques for three-dimensional reconstruction
(Formulations based on equivalent sources; calculation of plasma-wall gaps; halo current reconstruction)
4.5 Applications to existing devices and tokamaks under design
(Applications on ITER, FAST, MAST, JET, FTU and / or RFX
Magnetic control of plasma current, position, and shape in Tokamaks - A survey of modeling and control approaches
No full textPlasma current, position and shape control systems and modeling approaches were reviewed. The literature was divided into three categories, namely plasma radial position and current control, vertical stabilization of elongated plasmas, and plasma shape control. The plasma current and radial position control problem can be easily solved using a filament plasma model - the Shafarov lumped parameter equation and two separate PID controllers. At most, a MIMO controller can be used if decoupling is desired. Stabilization of the plasma vertical motion requires new control strategies in which the control algorithm is changed on the basis of an estimate of the measurement accuracy. For controlling the shape during the plasma formation and start-up phase, controllers based on magnetic flux control are useful when control requirements are not stringent
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