'Divertor' diaporamas de présentation

Progress and Outstanding Challenges in Tokamak Research

Progress and Outstanding Challenges in Tokamak Research. Michael Bell former Head of NSTX Experimental Research Operations Princeton Plasma Physics Laboratory Princeton University presented to the Joint ICTP-IAEA College on Plasma Physics

785 views • 42 slides

An upgrade for MAST

An upgrade for MAST. G. Cunningham for the MAST team EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK. MAST stands on two legs. DEMO physics. CTF. Strategic objective number 1: ST based component test facility (CTF). Indicative ST-CTF parameters:.

629 views • 37 slides

422 views • 32 slides

EU PPCS Models C & D Conceptual Design

443 views • 29 slides

Divertor Heat and Particle Control Experiments on the Large Helical Device

20 th PSI, Aachen. Divertor Heat and Particle Control Experiments on the Large Helical Device. S. Masuzaki for the LHD Experiment Group National Institute for Fusion Science. Introduction.

400 views • 29 slides

Progress of the EU Power Plant Conceptual Study (PPCS)

Progress of the EU Power Plant Conceptual Study (PPCS). US/Japan Workshop on Power Plant Studies and Related Advanced Technologies With EU Participation San Diego, 6-7 April 2002 D. Maisonnier (david.maisonnier@tech.efda.org). Outline of Presentation. PPCS Framework & Objectives

434 views • 29 slides

Status of HL-2A

Status of HL-2A. HL-2A Team (Presented by Longwen Yan). Southwestern Institute of Physics, Chengdu, China. Presentation for IEA PD and LT activities on May 21, 2007. OUTLINE. Introduction of HL-2A tokamak Auxiliary Heating & Fueling Systems Diagnostic systems Experimental progress

385 views • 26 slides

A.Sagara, J.Plasma Fusion Research, 74 (1998) pp.947-951.

288 views • 23 slides

Tungsten-copper Divertor Development For EAST

Tungsten-copper Divertor Development For EAST. Present by D. -M. Yao EAST-Divertor Group, ASIPP-Hefei, China 25 th Symposium on Fusion Engineering June 10-14, 2013, San Francisco, US. Outline. Plasma-facing components for EAST Necessity of W/Cu Divertor for EAST

562 views • 23 slides

NSTX-U

NSTX-U. Supported by. Overview of Strategy for Boundary Physics and PMI. Coll of Wm & Mary Columbia U CompX General Atomics FIU INL Johns Hopkins U LANL LLNL Lodestar MIT Lehigh U Nova Photonics ORNL PPPL Princeton U Purdue U SNL Think Tank, Inc. UC Davis UC Irvine UCLA

387 views • 22 slides

JET: A major scientific contribution to the conception and design of ITER

JET: A major scientific contribution to the conception and design of ITER. Prof. Francis Troyon Ex Chairman of the JET Scientific Council Ex Member of the ITER TAC former Director CRPP EPFL 25th JET Anniversary, Culham 20th May 2004.

315 views • 18 slides

AN UPDATE ON DIVERTOR HEAT LOAD ANALYSIS

AN UPDATE ON DIVERTOR HEAT LOAD ANALYSIS. T.K. Mau, A. Grossman, A.R. Raffray UC-San Diego H. McGuinness RPI ARIES-CS Project Meeting June 14-15, 2005 University of Wisconsin, Madison. 1. OUTLINE. Divertor design strategy Recent progress in divertor heat load analysis

309 views • 18 slides

PFC Activities in Alcator C-Mod

PFC Activities in Alcator C-Mod. G.M. Wright , H. Barnard, B. Lipschultz, D.G. Whyte, S. Wukitch Plasma Science & Fusion Center, MIT, Cambridge USA. Outline. Tungsten migration in the Alcator C-Mod divertor Sputtering scenario Melting scenario Discussion/Comparison

331 views • 18 slides

ITER Control System Technology Study

385 views • 17 slides

Particle control study towards burning plasma control in JT-60U

I-16. Particle control study towards burning plasma control in JT-60U. H. Takenaga 1) and the JT-60 Team 1) Japan Atomic Energy Agency 18th International Conference on Plasma Surface Interactions Toledo, Spain May 26-30, 2008. JT-60U.

328 views • 17 slides

?Depth profiles in redeposited layers and eroded area

9th ITPA meeting on SOL/divertor physics, Garching, May 7-10, 2007. Depth-profiling and thermal desorption of hydrogen isotopes for plasma facing carbon tiles in JT-60U (Long term hydrogen retention) T. Tanabe, Kyushu University. ?Deep penetration into the bulk

236 views • 16 slides

Design and R&D of Plasma Facing Components and Assessment of Divertor Performance

International Symposium on Plasma Surface Interactions 2008.5.26 Toledo, SPAIN. Design and R&D of Plasma Facing Components and Assessment of Divertor Performance S. Sakurai, H. Kawashima, S. Higashijima , K. Shimizu, K. Masaki, N. Asakura, T. Hayashi, Y. K. Shibama and A. Sakasai

280 views • 15 slides

Deposition in the MKII - Gas Box Divertor Deposition in Septum

Deposition in the MKII - Gas Box Divertor Deposition in Septum. M. Rubel, P. Coad, J. Likonen. OUTLINE General deposition pattern on MKII-GB tiles Septum Summary. Operation time ~ 18 months in both cases. 1. 8. inner. outer. 3. 7. 5. 4. GB. 6. MKII - GB. Mark II-A

237 views • 11 slides

Absolutely Calibrated Tangential Imaging of Divertor R. J. Maqueda X Science LLC

Absolutely Calibrated Tangential Imaging of Divertor R. J. Maqueda X Science LLC. Project Objectives (from proposal) Develop and implement an absolutely calibrated tangential visible imaging system for the lower divertor of NSTX-U.

193 views • 6 slides

Richard Nygren (Sandia)

289 views • 5 slides