27th IAEA Fusion Energy Conference - IAEA CN-258

Session

OV/5 Overview Magnetic Fusion

OV/5

23 Oct 2018, 16:40

Mahatma Mandir Conference Centre

570. Overview of HL-2A Recent Experiments

Dr Min Xu (CnSWIP)

23/10/2018, 16:40

OV - Overviews

Overview

Experiments on the HL-2A tokamak have been aimed at physics issues involved in advanced tokamaks and ITER since the last IAEA FEC. In particular, significant progresses have been made in the following areas: techniques and physics of ELM control, energetic-particle physics, MHD, disruption, multi-scale interactions, physics of advanced tokamak scenario, edge turbulence. Regarding to techniques...

355. Physics research on the TCV tokamak facility: from conventional to alternative scenarios and beyond

Dr Stefano Coda (CRPP-EPFL)

23/10/2018, 17:05

OV - Overviews

Overview

The research program of the TCV tokamak ranges from conventional to advanced tokamak scenarios and advanced divertor configurations, to exotic plasmas driven by theoretical insight, exploiting the device’s unique shaping capabilities. The facility is operated intensively both domestically and with EUROfusion support. The new 1-MW NBI has expanded the parameter range, now encompassing ELMy...

594. Overview of Operation and Experiments in the ADITYA-U Tokamak

Mr Rakesh Tanna (Institute For Plasma Research)

23/10/2018, 17:30

OV - Overviews

Overview

Ohmically heated circular limiter tokamak, ADITYA has been upgraded to a tokamak named ADITYA Upgrade (ADITYA-U) having open divertor configuration with divertor plates. Experiment research in ADITYA-U (R0 = 75 cm, a = 25 cm) has made significant progress, since last FEC 2016. After successful commissioning of ADITYA-U, the Phase-I plasma operations have been conducted from December 2016, with...

619. Tokamak research in Ioffe Institute

Dr Nikolai Bakharev (Ioffe Institute)

23/10/2018, 17:55

OV - Overviews

Overview

Research of various aspects of tokamak physics is conducted on small tokamaks at Ioffe Insitute in a wide range of experimental conditions: R/a=1.6, Bt=0.5(1.0) T, Ip=250(500) kA – Globus-M(M2), R/a=2.4, Bt=1.0 T, Ip=150 kA – TUMAN-3M, R/a=7.0, Bt=3.0 T, Ip=25 kA – FT-2 tokamaks. Results obtained in final Globus-M experimental campaign (before upgrade shutdown) with the 25% toroidal magnetic...

703. Overview of recent progress in understanding NSTX and NSTX-U plasmas & Overview of new MAST physics in anticipation of first results from MAST Upgrade

Dr Jonathan Menard

23/10/2018, 18:20

OV - Overviews

Overview

A. The mission of the spherical tokamak NSTX-U is to explore the physics that drives core and pedestal transport and stability at high-β and low collisionality, as part of the development of the ST concept towards a compact, low-cost ST-based Pilot Plant. NSTX-U will operate at up to 2 MA and 1 T with up to 10 MW of Neutral Beam Injection (NBI) power for 5 seconds with up to 4 MW of High...

470. Overview of new MAST physics in anticipation of first results from MAST Upgrade

Dr Jonathan Menard

23/10/2018, 18:35

OV - Overviews

Overview

MAST Upgrade will operate in 2018 with unique capabilities to explore plasma exhaust and alternative divertor configurations to address this key issue for DEMO.
Modelling of the interaction between filaments with BOUT++ indicates filaments separated by more than 5x their width move independently, and their velocity is slightly perturbed by if their separation is 1 width, suggesting radial...