Tokamak sphérique

thumb|Intérieur d'un tokamak sphérique. Un tokamak sphérique est un dispositif de confinement magnétique de plasma de type tokamak permettant d'obtenir des réactions de fusions de nucléons. Un tokamak sphérique a un solénoïde central beaucoup plus fin qu'un tokamak classique. Une telle installation serait susceptible d'être utilisée pour produire de l'électricité. Généralités Le fonctionnement se base sur le principe du tokamak traditionnel torique mais en fonction des expérimentations faites à ce jour, le rapport entre le rendement énergétique et le volume de plasma confiné serait d'un ordre supérieur et la stabilité du plasma serait aussi bien meilleure (certaines estimations évoquent un ordre 10 fois supérieur). La recherche est beaucoup plus jeune que celle sur les tokamaks toriques, les expériences sont en plus faible nombre et sur des dispositifs de plus petite taille. Les estimations sur les potentialités de ce type de tokamak restent donc à confirmer avant de pouvo

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Énergie de fusion nucléaire

vignette| L'expérience de fusion magnétique du Joint European Torus (JET) en 1991. L'énergie de fusion nucléaire est une forme de production d'électricité du futur qui utilise la chaleur produite par

Tokamak

thumb|Vue intérieure du tore du Tokamak à configuration variable (TCV), dont les parois sont recouvertes de tuiles de graphite. Un tokamak est un dispositif de confinement magnétique expérimental ex

Fusion par confinement magnétique

La fusion par confinement magnétique (FCM) est une méthode de confinement utilisée pour porter une quantité de combustible aux conditions de température et de pression désirées pour la fusion nucléa

PHYS-424: Plasma II

This course completes the knowledge in plasma physics that students have acquired in the previous two courses, with a discussion of different applications, in the fields of magnetic confinement and controlled fusion, astrophysical and space plasmas, and societal and industrial applications.

PHYS-443: Physics of nuclear reactors

In this course, one acquires an understanding of the basic neutronics interactions occurring in a nuclear fission reactor as well as the conditions for establishing and controlling a nuclear chain reaction.

ME-464: Introduction to nuclear engineering

This course is intended to understand the engineering design of nuclear power plants using the basic principles of reactor physics, fluid flow and heat transfer. This course includes the following: Reactor designs, Thermal analysis of nuclear fuel, Nuclear safety and Reactor dynamics

Simulation of bootstrap current in 2D and 3D ideal magnetic fields in Tokamaks

Wilfred Anthony Cooper, Jonathan Graves, Michael Pedro, Madhusudan Raghunathan, Olivier Sauter

We aim to simulate the bootstrap current for a MAST-like spherical tokamak using two approaches for magnetic equilibria including externally caused 3D effects such as Resonant Magnetic Perturbations (RMPs), the effect of toroidal ripple, and intrinsic 3D effects such as non-resonant internal kink modes. The first approach relies on known neoclassical coefficients in ideal MHD equilibria, using the Sauter[O.~Sauter et al, Phys. Plasmas 6, 2834, (1999)] expression valid for all collisionalities in axisymmetry, and the second approach being the quasi-analytic Shaing-Callen[K.~C.~Shaing and J.~D.~Callen, Phys. Fluids 26, 3315, (1983)] model in the collisionless regime for 3D. Using the ideal free-boundary magnetohydrodynamic code VMEC, we compute the flux-surface averaged bootstrap current density, with the Sauter and Shaing-Callen expressions for 2D and 3D ideal MHD equilibria including an edge pressure barrier with the application of resonant magnetic perturbations, and equilibria possessing a saturated non- resonant 1/1 internal kink mode with a weak internal pressure barrier. We compare the applicability of the self-consistent iterative model on the 3D applications and discuss the limitations and advantages of each bootstrap current model for each type of equilibrium.

International Atomic Energy Agency2015

Chargement

Simulation of bootstrap current in 2D and 3D ideal magnetic fields in tokamaks

Wilfred Anthony Cooper, Jonathan Graves, Michael Pedro, Madhusudan Raghunathan, Olivier Sauter

We aim to simulate the bootstrap current for a MAST-like spherical tokamak using two approaches for magnetic equilibria including externally caused 3D effects such as resonant magnetic perturbations (RMPs), the effect of toroidal ripple, and intrinsic 3D effects such as non-resonant internal kink modes. The first approach relies on known neoclassical coefficients in ideal MHD equilibria, using the Sauter (Sauter et al 1999 Phys. Plasmas 6 2834) expression valid for all collisionalities in axisymmetry, and the second approach being the quasi-analytic Shaing–Callen (Shaing and Callen 1983 Phys. Fluids 26 3315) model in the collisionless regime for 3D. Using the ideal free-boundary magnetohydrodynamic code VMEC, we compute the flux-surface averaged bootstrap current density, with the Sauter and Shaing–Callen expressions for 2D and 3D ideal MHD equilibria including an edge pressure barrier with the application of resonant magnetic perturbations, and equilibria possessing a saturated non-resonant 1/1 internal kink mode with a weak internal pressure barrier. We compare the applicability of the self-consistent iterative model on the 3D applications and discuss the limitations and advantages of each bootstrap current model for each type of equilibrium.

2016

Chargement

Simulation of bootstrap current in 2D and 3D ideal magnetic fields in tokamaks

Wilfred Anthony Cooper, Jonathan Graves, Michael Pedro, Madhusudan Raghunathan, Olivier Sauter

We aim to simulate the bootstrap current for a MAST-like spherical tokamak using two approaches for magnetic equilibria including externally caused 3D effects such as resonant magnetic perturbations (RMPs), the effect of toroidal ripple, and intrinsic 3D effects such as non-resonant internal kink modes. The first approach relies on known neoclassical coefficients in ideal MHD equilibria, using the Sauter (Sauter et al 1999 Phys. Plasmas 6 2834) expression valid for all collisionalities in axisymmetry, and the second approach being the quasi-analytic Shaing-Callen (Shaing and Callen 1983 Phys. Fluids 26 3315) model in the collisionless regime for 3D. Using the ideal free-boundary magnetohydrodynamic code VMEC, we compute the flux-surface averaged bootstrap current density, with the Sauter and Shaing-Callen expressions for 2D and 3D ideal MHD equilibria including an edge pressure barrier with the application of resonant magnetic perturbations, and equilibria possessing a saturated non-resonant 1/1 internal kink mode with a weak internal pressure barrier. We compare the applicability of the self-consistent iterative model on the 3D applications and discuss the limitations and advantages of each bootstrap current model for each type of equilibrium.

Iop Publishing Ltd2016

Chargement