Mr
SUNIL BELSARE
(INSTITUTE FOR PLASMA RESEARCH)
22/10/2018, 14:00
OV - Overviews
Overview Poster
Plasma facing components (PFCs) of ITER-like tokamak are expected to subject high heat loads up to 10MW/m^2 during the tokamak operation in steady state condition. Selection of plasma facing materials/components required extensive qualification and testing for tokamak application. High Heat Flux Test Facility (HHFTF) plays an important role for the qualification and estimation of the life of...
Prof.
Troy Carter
(University of California, Los Angeles)
22/10/2018, 14:00
OV - Overviews
Overview Poster
Studies of turbulence and transport in the Large Plasma Device (LAPD)
have: documented the role of drift-Alfvén waves and flows in avalanche
events; revealed a new instability in the edge of increased β plasmas;
and demonstrated an interaction between ICRF waves and edge
turbulence, leading to strong modulation of the former and enhancement
of the latter. Intermittent collapses of the...
Dr
Mayur Kakati
(Centre of Plasma Physics-Institute for Plasma Research, Sonapur, Assam, India)
22/10/2018, 14:00
OV - Overviews
Overview Poster
It is important to understand how the plasma with unparalleled heat (~10MWm-2) and ion (~1024 m-2s-1) flux will interact with the tungsten walls in the ITER tokamak, more specifically at the Divertor region of the fusion machine. Several linear magnetized plasma devices have been developed worldwide that reproduced ITER Divertor like extreme conditions for studies on relevant plasma surface...
Hiroshi Gota
(TAE Technologies, Inc.)
22/10/2018, 14:00
OV - Overviews
Overview Poster
TAE's research has been devoted to producing a high temperature, stable, long-lived field-reversed configuration (FRC) plasma state by neutral-beam injection (NBI) and edge biasing/control. C-2U experiments have demonstrated drastic improvements in particle and energy confinement properties of FRC's, and the plasma performance obtained via ~10 MW NBI has achieved plasma sustainment of up to 5...
Dr
Jonathan Menard
(Princeton Plasma Physics Laboratory)
22/10/2018, 14:00
OV - Overviews
Overview Poster
The spectrum of scientific and technological gaps that must be closed to achieve practical fusion energy using magnetically confined plasmas has been extensively documented. A common barrier to narrowing or closing these gaps is the scale and cost of fusion facilities needed to address the gaps. The low-aspect-ratio “spherical torus/tokamak” (ST) is being explored world-wide as a potentially...
Dr
Michael Komm
(Institute of Plasma Physics of the Czech Academy of Sciences)
22/10/2018, 14:00
OV - Overviews
Overview Poster
In the years 2016-17 the research on the COMPASS tokamak was focused on support of solution of the key challenges for the design and operation of ITER and next-step devices. This included mainly installations and upgrades of state-of-art edge plasma diagnostics, such as the new divertor probe array and the High Resolution Thomson scattering. Strong emphasis was placed on development of...
Bahukutumbi P. Radha
(University of Rochester)
22/10/2018, 14:00
OV - Overviews
Overview Poster
Direct-drive (DD) inertial confinement fusion (ICF) offers a potential path for high yield and ignition. Two approaches – Laser Direct Drive (LDD), being pursued primarily at the OMEGA laser and the National Ignition Facility (NIF), and the Magnetized Liner Inertial Fusion (MagLIF), being pursued primarily at the Sandia National Laboratories, will be discussed in this talk. In LDD nominally...
Prof.
Wandong Liu
(University of Science and Technology of China)
22/10/2018, 14:00
OV - Overviews
Overview Poster
The Keda Torus eXperiment (KTX) is a new built middle-size reversed field pinch (RFP) device at the University of Science and Technology of China. After the long time conditioning, the favorable wall condition is achieved for implementing experiment on KTX. In present, the maximum plasma current can reach 200kA, the discharge length is beyond 20ms and the duration of typical reversed field...
Dr
Gianluca Pucella
(ENEA)
22/10/2018, 14:00
OV - Overviews
Overview Poster
Since the 2016 IAEA FEC Conference, FTU operations have been mainly devoted to experiments on runaway electrons and investigations about a tin liquid limiter; other experiments have involved the elongated plasmas and dust studies. The tearing mode onset in the high density regime has been studied by means of the linear resistive code MARS and the highly collisional regimes have been...
Dr
Nengchao Wang
(International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics (IFPP), AEET, SEEE, CnHUST)
22/10/2018, 14:00
OV - Overviews
Overview Poster
Recent J-TEXT research has highlighted the significance of the role that non-axisymmetric magnetic perturbations, so called 3D magnetic perturbation (MP) fields, play in fundamentally 2D concept, i.e. tokamak. In this paper, the J-TEXT results achieved over the last two years, especially on the impacts of 3D MP fields on magnetic topology, plasma disruptions, MHD instabilities, and plasma...
