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

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.

By giverny
(122 views)

EU PPCS Models C & D Conceptual Design

EU PPCS Models C & D Conceptual Design

Institut für Materialforschung III. EU PPCS Models C & D Conceptual Design. Presented by P. Norajitra , FZK . PPCS Design Studies – Strategy definition [D. Maisonnier]. 2 models with “limited” extrapolations Model A: WCLL (water cooled lithium lead) [P. Sardain]

By garren
(144 views)

ITER Control System Technology Study

ITER Control System Technology Study

ITER Control System Technology Study. Klemen Žagar klemen.zagar@cosylab.com. Overview. About ITER ITER Control and Data Acquisition System (CODAC) architecture Communication technologies for the Plant Operation Network Use cases/requirements Performance benchmark. A Note!.

By adia
(194 views)

Progress and Outstanding Challenges in Tokamak Research

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

By torgny
(279 views)

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

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.

By gala
(137 views)

Key Issues in Plasma-Wall Interactions for ITER The European Approach 

Key Issues in Plasma-Wall Interactions for ITER The European Approach 

EU-PWI-Task Force. Key Issues in Plasma-Wall Interactions for ITER The European Approach  V. Philipps, J. Roth, A. Loarte  With Contributions G.F Matthews H.G.Esser G. Federici J.P.Coad U.Samm M. Mayer J.Strachan P.Wienhold P.Andrew M.Stamp A. Kirschner G. Pautasso

By doctor
(97 views)

Status of HL-2A

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

By kaida
(119 views)

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

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.

By ingo
(128 views)

☆Depth profiles in redeposited layers and eroded area

☆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

By aggie
(69 views)

AN UPDATE ON DIVERTOR HEAT LOAD ANALYSIS

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

By della
(128 views)

An upgrade for MAST

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:.

By cruz
(239 views)

PFC Activities in Alcator C-Mod

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

By lynn
(127 views)

Divertor Heat and Particle Control Experiments on the Large Helical Device

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.

By lavina
(98 views)

Deposition in the MKII - Gas Box Divertor Deposition in Septum

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

By danno
(119 views)

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

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

By marinel
(115 views)

Tungsten-copper Divertor Development For EAST

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

By paniz
(188 views)

Richard Nygren (Sandia)

Richard Nygren (Sandia)

Concerns on Integration of A Liquid Metal Divertor. Richard Nygren (Sandia). Heat load D/T and He pumping Plumbing/configuration Safety & Maintenance. CLIFF Concept. “flow convertor” modifies flow for divertor. APEX Program - Divertor Integration Subtask. Heat Removal.

By aquila
(236 views)

NSTX-U

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

By brigit
(160 views)

Progress of the EU Power Plant Conceptual Study (PPCS)

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

By brigit
(130 views)

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