'Energy confinement' diaporamas de présentation

Transport and fluctuations in LHD and comparisons with tokamaks

ITPA CDBM and Transport meetings - Spring 2007 at EPFL Lausanne. Transport and fluctuations in LHD and comparisons with tokamaks.

553 views • 46 slides

A Few Comments About Fusion

A Few Comments About Fusion. Binding Energy. Energy released when nucleus created from protons and neutrons Larger binding energy per nucleon means more stable nucleus. Fusion vs. Fission. Fission. Fusion. Relevant fusion reactions. Calculation of energy released .

576 views • 35 slides

Relay Feedback and X-poin t Height Control

NSTX. Supported by . Relay Feedback and X-poin t Height Control. College W&M Colorado Sch Mines Columbia U CompX General Atomics INL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U SNL Think Tank, Inc.

399 views • 30 slides

Confinement and MHD Stability in the Large Helical Device

OV1-4. Confinement and MHD Stability in the Large Helical Device. Osamu Motojima LHD Experimental Group National Institute for Fusion Science. IAEA2004, Vilamoura, Portugal, Nov. 1 , 2004. Content of my paper. 1. Change of NIFS Organization 2. MHD study 2.1. High beta experiment

337 views • 24 slides

Design Description of the Coaxial Helicity Injection (CHI) System on NSTX-U

NSTX. Supported by . Design Description of the Coaxial Helicity Injection (CHI) System on NSTX-U. College W&M Colorado Sch Mines Columbia U Comp-X General Atomics INL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U

404 views • 23 slides

Discussion of PFC/particle/lithium plans for NSTX-U

NSTX-U. Supported by . Discussion of PFC/particle/lithium plans for NSTX-U. J. Menard for the NSTX Research Team. Columbia U CompX General Atomics FIU INL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U ORNL PPPL Princeton U Purdue U SNL

325 views • 19 slides

Direct Profile Extrapolation Method for the Deductive Procedure of Fusion Reactor Design

US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies with participations of EU and Korea ? 22-24 Feb. 2011 ?. Direct Profile Extrapolation Method for the Deductive Procedure of Fusion Reactor Design. J. Miyazawa National Institute for Fusion Science, Japan.

338 views • 18 slides

271 views • 14 slides

Japan Atomic Energy Agency Naka Fusion Institute

Japan Atomic Energy Agency Naka Fusion Institute. EX/5-1. Enhanced H-mode Pedestal and Energy Confinement by Reduction of Toroidal Field Ripple in JT-60U. H. Urano, N. Oyama, K. Kamiya, Y. Koide, H. Takenaga, T. Takizuka, M. Yoshida, Y. Kamada and the JT-60 Team.

269 views • 13 slides

Transport Barriers and H-mode in Regimes with Deuterium Pellets Injected into T-10 Plasma Heated by ECR A . A . Borschegovskiy, M . M . Dremin ,, A . M . Kakurin , S . V . Krylov , M . Yu . Nikulin , Yu.D.Pavlov, I . N . Roy, V . A . Zhuravlev.

265 views • 13 slides