Prof.
Francisco Castejón
(CIEMAT)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Recent improvements in diagnostics and operation have led to better understanding of 3-D effects on transport and plasma control in the TJ-II stellarator. Impurity transport: Direct measurments of electrostatic potential variations within the same magnetic flux surface in ECRH plasmas are presented. Calculations show that such asymmetries affect impurity accumulation. The asymmetry value and...
Prof.
Hiroshi AZECHI
(Institute of Laser Engineering, Osaka University)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Here we report recent progress of the fast ignition inertial confinement fusion demonstration. Fraction of low energy (< 1 MeV) component of the relativistic electron beam (REB), which efficiently heats the fuel core, increases by the factor of 4 by enhancing pulse contrast of heating laser and removing preformed plasma sources. Kilo-tesla magnetic field is studied to guide the diverging REB...
Dr
Wayne M. Solomon
(Princeton Plasma Physics Laboratory)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The DIII-D tokamak has addressed key issues to advance the physics basis for burning plasmas for ITER and future steady-state fusion devices. Developments on ITER scenarios include the discovery of a new wide-pedestal variant of QH-mode where increased edge transport is found to allow higher pedestal pressure, consistent with peeling-ballooning theory, and complete ELM suppression in...
Prof.
Sergei Krasheninnikov
(University California San Diego)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The processes involving edge plasma and plasma-material interactions in magnetic fusion devices are very multifaceted and include a wide spectrum of phenomena ranging from plasma turbulence and meso-scale stability, recycling and transport processes of hydrogen species in the wall material, to the modification of wall material properties. In many cases these processes are strongly coupled and...
Yasuhiko Takeiri
(National Institute for Fusion Science)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The final goal of the LHD project is to obtain the high performance helical plasma relevant to the fusion reactor, i.e., ion and electron temperature T_i > 10 keV, volume averaged beta > 5 %, fusion triple product n_e tau_E Ti > 1020 keV m^-3 s, and long pulse length of more than 3600 s with heating power of 3 MW. In order to achieve this objective, the deuterium plasma is expected to have...
Prof.
Robert Wolf
(Max-Planck-Institute for Plasma Physics)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The main objective of the optimized stellarator Wendelstein 7-X (W7-X) is the demonstration of steady-state plasma operation at fusion relevant plasma parameters thereby verifying that the stellarator is a viable fusion power plant concept. The design of W7-X is based on an elaborate optimization procedure to overcome the shortcomings of the concept. After completing the main construction...
Prof.
Raymond Fonck
(University of Wisconsin-Madison)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Studies at near-unity aspect ratio offer unique insights into the high confinement (H-mode) regime and support development of novel startup scenarios. Ohmic H-mode operation has been attained at A < 1.3. Edge plasma parameters permit probe measurements of the edge pedestal, including the local current density profile, with high spatial and temporal resolution. H-mode plasmas have standard L-H...
Prof.
Kimitaka Itoh
(NIFS)
17/10/2016, 14:00
OV - Overviews
Overview Poster
This article assesses the understanding of and impacts by the hysteresis of transport relation. The rapid changes of fluxes compared to slow changes of plasma parameters are overviewed for both edge barrier and core plasmas. The theoretical approaches to understand the direct influence of heating power on turbulent transport are addressed. The advanced data analysis method to search the...
Mr
Paul Wouters
(Fusion For Energy)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The ITER project is being undertaken at Cadarache, France, to construct and operate an experimental nuclear fusion facility. The aim of this paper is the description of the implementation of the French Order of February 7, 2012, concerning Nuclear Installation (called Installation Nuclear de Base, INB) in France within the European Domestic Agency (EU-DA). For protection of Public Safety,...
Prof.
Boris Breizman
(The University of Texas at Austin)
17/10/2016, 14:00
OV - Overviews
Overview Poster
This overview talk covers recent developments in the theory of runaway electrons in tokamaks. Such electrons are known to be of serious concern with regard to safe operation of large-scale tokamaks in general and ITER in particular. They can quickly replace a large part of the bulk electron current during disruptions, and the corresponding magnetic energy exceeds the particle kinetic energy....
Dr
Arne Kallenbach
(Max-Planck-Institut f. Plasmaphysik)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The ASDEX Upgrade program is devoted to the preparation of ITER operation and the development of plasma scenarios and physics understanding for a future DEMO. Different scenario lines adapted to critical research tasks are developed and naturally integrated with the metallic, high-Z plasma facing components environment. The scenarios can be mainly divided into low core collisionality and high...
Prof.
Yican Wu
(Institute of Nuclear Energy Safety Technology (INEST),Chinese Academy of Sciences)
17/10/2016, 14:00
OV - Overviews
Overview Poster
A fusion DEMO reactor, like other advanced nuclear energy systems, must satisfy several goals including a high level of public and worker safety, low environmental impact, high reactor availability, a closed fuel cycle, and the potential to be economically competitive. The experience of the ITER project will facilitate DEMO programs in developing a safety approach and a safety design,...
Dr
Baonian Wan
(Institute of Plasma Physics, Chinese Academy of Sciences)
17/10/2016, 14:00
OV - Overviews
Overview Poster
EAST aims to demonstrate steady-state advanced high-performance H-mode plasmas with ITER-like configuration, plasma control and heating schemes. Since 2015, EAST has been equipped with all ITER-related auxiliary heating and current drive systems. Two NBI systems injected from Co- and Ctr-current directions, have been installed on EAST and allow the flexible study of the plasma rotation effect....
Dr
Jonathan Menard
(Princeton Plasma Physics Laboratory)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The National Spherical Torus Experiment (NSTX) has undergone a major upgrade, and NSTX Upgrade (NSTX-U) is now the most capable Spherical Torus/Tokamak (ST) in the world program. NSTX-U mission elements include: exploring unique ST parameter regimes to advance predictive capability for ITER and beyond, developing solutions for the plasma-material interface challenge, and advancing the ST as a...
Dr
Earl Marmar
(Mass. Inst. of Technology)
17/10/2016, 14:00
OV - Overviews
Overview Poster
C-Mod is the only divertor tokamak in the world capable of operating at B fields up to 8 T, equaling and exceeding that planned for ITER. C-Mod is compact, thus accessing regimes of extreme edge power density (1 MW/m2 average through the plasma surface). Scrape-off layer (SOL) power widths are of order of a few mm, with measured parallel power flows >1 GW/m2 at the divertor, surpassing the...
Prof.
John Sarff
(University of Wisconsin-Madison)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The reversed field pinch (RFP) offers unique capabilities that could be essential to closing gaps to fusion power. The RFP has large plasma current and small toroidal field, with q(r)<1. Two key benefits arise: (1) the possibility for ohmic heating to ignition and (2) minimization of the field strength at the magnets. The material boundary can be made invisible to an inductive electric field,...
Dr
Hendrik Meyer
(CCFE)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Progress in tackling the edge challenge within the new European Medium Size Tokamak Task Force (EU-MST) will be reported. EU-MST coordinates research on ASDEX Upgrade, MAST and TCV supported by the local teams. The challenge is approached from two directions. On the one hand plasma regimes reducing the transient heat loads whilst trying to maintain high confinement are developed with active...
Dr
Renaud Dejarnac
(CzIPP)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The COMPASS tokamak is one of the present devices operating with an ITER-like plasma shape. Its flexibility combined to an extensive set of diagnostics and NBI heating allow to address a broad range of key areas in support of the worldwide fusion programme such as H-mode, MHD, RAE, disruptions, PWI. The recent results obtained in COMPASS addressing these key issues are reviewed here.
The...
Mr
Rakesh Tanna
(Institute For Plasma Research)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Several experiments, related to controlled thermonuclear fusion research and highly relevant for large size tokamaks including ITER, have been carried out in ADITYA, an ohmically heated circular limiter tokamak. Repeatable plasma discharges of maximum plasma current of ~ 160 kA and discharge duration beyond ~ 250 ms with plasma current flattop duration of ~ 140 ms has been obtained for the...
Prof.
Xuru Duan
(Southwestern Institute of Physics)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Recent experiments on the HL-2A tokamak have been aimed at the major challenges relevant to ITER operation and fusion energy development. Significant progress has been achieved in many areas, including the first demonstration of high coupling efficiency of LHCD passive-active multi-junction (PAM) antenna in H-mode discharges, pedestal instability and dynamics, ITB formation mechanism,...
Dr
Andrew Kirk
(Culham Centre for Fusion Energy)
17/10/2016, 14:00
OV - Overviews
Overview Poster
New results from MAST will be presented that focus on validating models in order to extrapolate to future devices. Particular attention will be given to the areas of scenario development, fast particle physics and plasma exhaust. Understanding filamentary transport across the scrape off layer is a key issue for the design and operation of future devices as it is crucial in determining the...
Dr
Duarte Borba
(EUROfusion Programme Management Unit, Culham Science Center, Abingdon, UK)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Following the successful operation of a European High Performance Computer For Fusion applications (HPC-FF) in Jülich, Germany, from 2009 to 2013, a new supercomputer dedicated to magnetic fusion research was procured within the Broader Approach agreement between Europe and Japan. The new platform, “Helios”, was installed in the International Fusion Energy Research Centre - Computational...
Prof.
Yuichi Takase
(University of Tokyo)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Nationally coordinated research on spherical tokamak (ST) is being conducted in Japan, to strengthen the scientific basis and to broaden future options of ST applications. The research themes to concentrate on are (1) the physics of very high beta plasmas, (2) development of start-up, current drive, and control techniques without the use of the central solenoid (CS), and (3) demonstration of...
Dr
Subrata Pradhan
(Institute for Plasma Research)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Steady State Superconducting Tokamak (SST-1) is a `operational’ experimental superconducting device since late 2013. Since last IAEA-FEC; SST-1 has been upgraded with Plasma Facing Components being installed and integrated in the vacuum vessel and is getting prepared towards long pulse operations in both circular and elongated configurations. The PFC integration has been completed in August...
Dr
Gianluca Pucella
(ENEA)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Experiments of Electron Cyclotron (EC) assisted breakdown have shown the presence of runaway electrons (RE) also below the Dreicer electric field threshold, indicating that the RF power acts as seeding for fast electrons, and a large database of post-disruption generated RE beams has been analysed in order to identify linear dynamical models for new position and current RE beam controllers. A...
Dr
juan knaster
(IFMIF/EVEDA)
17/10/2016, 14:00
OV - Overviews
Overview Poster
IFMIF, the International Fusion Materials Irradiation Facility, presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the Broader Approach Agreement, will allow accelerated testing of structural materials with fusion relevant neutrons at >20dpa/year in 500cm3. IFMIF consists of two 125 mA and 40 MeV D+ linear accelerators operating in CW mode. The...
Dr
xavier Litaudon
(EUROfusion)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The JET contributors
Europe has elaborated a Roadmap to the realisation of fusion energy in which ‘ITER is the key facility and its success is the most important overarching objective of the programme’. We review the contribution of the recent JET experiments with the ITER first wall materials mix, and, the underlying physics understanding to mitigate the scientific risks identified in the...
Dr
Yeong-Kook Oh
(National Fusion Research Institute)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The KSTAR device has been operated since the first plasma in 2008 with the mission of exploring the physics and technologies of high performance steady-state operation that are essential for ITER and fusion reactor. KSTAR has been focusing on maximizing performance and extending pulse length targeting H-mode dischage up to 300s at higher plasma current up to 2 MA, and at higher normalized beta...
Prof.
Yuanxi WAN
(Institute of Plasama Physics, Chinese Academy of Sciences)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The Chinese Fusion Engineering Testing Reactor (CFETR) is the next device for the Chinese magnetic confinement fusion (MCF) program which aims to bridge the gaps between the fusion experiment ITER and the demonstration reactor DEMO. CFETR will be operated in two phases: Steady-state operation and tritium self-sustainment will be the two key issues for the first phase with a modest fusion power...
Dr
Matteo Zuin
(Consorzio RFX, Padova, Italy)
17/10/2016, 14:00
OV - Overviews
Overview Poster
Thanks to its flexibility and unique control capability, the RFX-mod device has been operated in the last two years to investigate a wide range of experimental conditions. Reversed-Field Pinch (RFP), Tokamak and the full range of magnetic configurations in between the two, the ultra-low q, have been produced to contribute to physics common topics highlighting similarities and/or peculiarities....
Dr
Stefano Coda
(CRPP-EPFL)
17/10/2016, 14:00
OV - Overviews
Overview Poster
A broad upgrade program is underway at the TCV tokamak. A historic first step is the present commissioning of the first neutral beam injector (NBI), delivering 1 MW of power at energies in the 15-30 keV range. Four gyrotrons are also being added in 2016-2018 to bring the total ECRH power to 6 MW. A second, counter-injected, 1-MW neutral beam is also planned, in addition to the introduction of...
Mr
Bernard Bigot
17/10/2016, 14:00
OV - Overviews
Overview Poster
The ITER project is a critical step in the development of fusion energy: its role is to confirm the feasibility of exploiting magnetic confinement fusion for the production of energy for peaceful purposes by providing an integrated demonstration of the physics and technology required for a fusion power plant. Rapid progress is being made in the design, manufacturing, construction and R&D...
Mr
Ge Zhuang
(Huazhong University of Science and Technology)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The progress of experimental research over last two years on the J-TEXT tokamak is reviewed, the most significant results including: the investigation of the effect of resonant magnetic perturbations (RMPs) on the J-TEXT operation region, impurity transport and confinement, and runaway electrons suppression; study of the threshold for runaway current generation; and identification of the...
Dr
Hiroshi SHIRAI
(Japan Atomic Energy Agency)
17/10/2016, 14:00
OV - Overviews
Overview Poster
The JT-60SA project has been promoted since June 2007 under the framework of the Broader Approach (BA) agreement and Japanese national fusion programme for an early realization of fusion energy by conducting supportive and complementary work for the ITER project and directing DEMO design activity. With the powerful and varied deposition profile of heating and current drive system, flexible...
Mr
Dmitrii Sarychev
(NRC "Kurchatov Institute")
17/10/2016, 14:00
OV - Overviews
Overview Poster
Review of the recent experimental results obtained on the T-10 tokamak is presented. To decrease the level of light impurities in 2015 both the rail and circular limiters were replaced with ones made of tungsten. The used tungsten type «POLEMA» as well as the technology of its soldering to the bronze substrate are similar to those applied for the production of the ITER divertor tiles. In the...
Dr
Michael John Edwards
(Lawrence Livermore National Laboratory)
17/10/2016, 14:00
OV - Overviews
Overview Poster
M. J. Edwards1, T. C. Sangster2, D. B. Sinars3 1 Lawrence Livermore National Laboratory, Livermore, CA 94551, USA 2 Laboratory for Laser Energetics, 250 E. River Rd, Rochester, NY 14623-1299, USA 3 Sandia National Laboratories, Albuquerque, NM 87185, USA
Ignition and significant fusion yield from Inertial Confinement Fusion (ICF) remains a grand scientific challenge. The ICF community in the...
