'Divertor heat' presentation slideshows

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.

399 views • 29 slides

Masayuki Ono NSTX-U Project Director PPPL, Princeton University

NSTX-U. Supported by. Plasma-Wall Boundary Control With Lithium Divertor and Associated Plasma Confinement Improvements in NSTX. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA

469 views • 29 slides

Masayuki Ono NSTX-U Project Director PPPL, Princeton University

NSTX-U. Supported by. Plasma-Wall Boundary Control With Lithium Divertor and Associated Plasma Confinement Improvements in NSTX. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA

296 views • 29 slides

NSTX-U Status and Plan

NSTX-U. Supported by. NSTX-U Status and Plan. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA Hebrew U Ioffe Inst RRC Kurchatov Inst TRINITI NFRI KAIST POSTECH Seoul National U

371 views • 28 slides

Advanced divertor configurations with large flux expansion

Advanced divertor configurations with large flux expansion. V. A. Soukhanovskii Lawrence Livermore National Laboratory, Livermore, California, USA H. Reimerdes

371 views • 26 slides

Divertor heat flux reduction and detachment in NSTX

Office of Science. Supported by. Divertor heat flux reduction and detachment in NSTX. V. A. Soukhanovskii 1 , R. Maingi 2 , R. Raman 3 , C. E. Bush 2 , R. E. Bell 4 , R. Kaita 4 , H. W. Kugel 4 , C. J. Lasnier 1 , B. P. LeBlanc 4 , J. Menard 4 , S. F. Paul 4 , A. L. Roquemore 4 ,

458 views • 25 slides

Masayuki Ono NSTX-U Project Director PPPL, Princeton University

NSTX-U. Supported by. Plasma-wall boundary control with lithium divertor and associated plasma confinement improvements in NSTX ???. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA

469 views • 24 slides

Masayuki Ono NSTX-U Project Director PPPL, Princeton University

NSTX-U. Supported by. Plasma-wall boundary control with lithium divertor and associated plasma confinement improvements in NSTX ???. Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U Tsukuba U U Tokyo JAEA

250 views • 24 slides

Mission and Design Requirements on National Centralized Tokamak (NCT)

359 views • 22 slides

1) Disruption heat loading 2) Progress on time-dependent modeling

1) Disruption heat loading 2) Progress on time-dependent modeling . C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD, 4/4/2011. Continuing the loading description for PFCs. divertor/heat nominal nominal transient off-normal transient

230 views • 13 slides