Mr
Masahiro Kobayashi
(Japan)
13/10/2014, 14:00
Overview Poster
This paper overviews recent progress on the experimental identification and physics interpretation of 3D effects of magnetic field geometry/topology on divertor transport in helical devices and tolamaks with RMP. The 3D effects are elucidated as a consequence of competition between transports parallel (//) and perpendicular to magnetic field, in open field lines cut by divertor plates or in...
Mr
Baonian Wan
(China)
13/10/2014, 14:00
Overview Poster
Since the last IAEA-FEC, significant progress has been made on EAST on both physics and technology fronts towards the long-pulse operation of high-confinement plasma regimes. EAST has been upgraded with more than 25 MW of CW heating & current drive power, along with 70 diagnostics, two internal cryopumps, an ITER-like W monoblock top divertor and resonant magnetic perturbation coils, which...
Mr
Earl Marmar
(USA)
13/10/2014, 14:00
Overview Poster
Alcator C-Mod studies high-field, high-performance diverted plasmas in support of ITER and steps beyond, focussing on RF and microwave tools for heating and current drive, with all metal high-Z plasma-facing components. Stability analysis of pedestals in the I-mode regime finds that pressures are well below the peeling-ballooning limit, as well as expected kinetic ballooning mode thresholds,...
Prof.
Mikhail Gryaznevich
(Tokamak Energy Ltd; 6Technical University of Denmark, DTU Risø, Roskilde, Denmark; Imperial College, London, UK)
13/10/2014, 14:00
OV - Overviews
Overview Poster
IAEA Coordinated Research Projects (CRP) on “Utilisation of a Network of Small Magnetic Confinement Fusion Devices for Mainstream Fusion Research” and “Conceptual development of steady-state compact fusion neutron sources” continue to contribute to the mainstream Fusion Research. These CRPs join participants from 18 IAEA member states, who perform experiments and present results of individual...
Mr
Richard J. Buttery
(USA)
13/10/2014, 14:00
Overview Poster
The DIII-D tokamak has addressed key challenges in preparation for ITER and the next generation of fusion devices. The robustness of RMP-ELM suppression was demonstrated using as few of 5 of the usual 12 coils. QH mode was extended to 80% Greenwald density fraction, establishing its viability for ITER. Disruption mitigation led to relatively symmetric non-localized heat loads, while vertical...
Mr
Hiroshi AZECHI
(Japan)
13/10/2014, 14:00
Overview Poster
Fast ignition has high potential to ignite a fusion fuel with only about one tenth of laser energy necessary for the central ignition. One of the most advanced fast ignition programs is the Fast Ignition Realization Experiment (FIREX). The goal of its first phase is to demonstrate ignition temperature of 5 keV, followed by the second phase to demonstrate ignition-and-burn. Relativistic fast...
Mr
Subrata Pradhan
(India)
13/10/2014, 14:00
Overview Poster
Steady State Superconducting Tokamak (SST-1) has been commissioned after the successful experimental and engineering validations of its critical sub-systems. During the `engineering validation phase’ of SST-1; the cryostat was demonstrated to be leak tight to superconducting magnets system operations in all operational scenarios, the 80 K thermal shield was demonstrated to be uniformly cooled...
Mr
Leonid Askinazi
(Russian Federation)
13/10/2014, 14:00
Overview Poster
Overview of activity of the Plasma Physics Division at the Ioffe Institute in support of fusion program is presented. Experiments on LHCD (100kW, 2.5GHz) at the Globus-M tokamak (R=0.36m, a=0.24m, B_tor=0.4T, I_pl=200kA) with poloidally oriented grill resulted in RF driven current of up to 40 kA, in agreement with the theory predictions. At the FT-2 tokamak (R=0.56m, a=0.08m, B_tor=2.3T,...
Mr
Noriyoshi Nakajima
(Japan)
13/10/2014, 14:00
OV - Overviews
Overview Poster
In order to complement ITER and contribute to an early realization of the DEMO reactor, International Fusion Energy Research Centre (IFERC) implements DEMO Design and Research and Development activities. The design basis for DEMO and the sensitivity to underlying physics and technology assumptions has been reviewed through a 3-year collaboration. At this point, the plasma major radius and net...
Mr
Paul Terry
(USA)
13/10/2014, 14:00
Overview Poster
Recent results on electromagnetic turbulence from gyrokinetic studies in different magnetic configurations are overviewed, showing the characteristics of electromagnetic turbulence and
transport in situations where it is both expected and unexpected, and showing how it is affected by equilibrium magnetic field scale lengths. Ballooning parity ion temperature gradient (ITG) turbulence is found...
Mr
Min Xu
(China)
13/10/2014, 14:00
Overview Poster
Since the last IAEA FEC, experiments on HL-2A tokamak have been dedicated to address the physics on L-H transition, energetic-particles (EPs) and shear Alfvén waves (SAWs), ELM mitigation, disruption mitigation, edge impurity transport and other MHD related activities. In particular, significant progresses have been made in the following areas: (i) For the first time in experiments, it was...
Mr
Si-Woo Yoon
(Korea, Republic of)
13/10/2014, 14:00
Overview Poster
Since the initial long-pulse H-mode operation in 2012, the H-mode has been sustained longer and the operational regime of plasma parameters has been significantly extended in KSTAR tokamak. The progress in long-pulse operation is mainly due both to the increased NBI heating power of PNBI ~ 3.5 MW and the advance in the shaping control which is not trivial with slow superconducting coils. In...
Mr
Ian Chapman
(UK)
13/10/2014, 14:00
Overview Poster
n=2,3,4,6 has been demonstrated: at higher and lower collisionality; for the first ELM; during the current ramp-up; when a sub-set of in-vessel coils fail; and with rotating n=3 RMPs. n=4,6 fields cause less braking whilst the power to access H-mode is less with n=4 than n=3,6. Refuelling with gas or pellets gives plasmas with mitigated ELMs and reduced peak heat flux whilst less than 10% drop...
Mr
Stanley Kaye
(USA)
13/10/2014, 14:00
Overview Poster
NSTX is currently being upgraded to operate at twice the toroidal field and plasma current (up to 1 T and 2 MA), with a second, more tangentially aimed neutral beam for current and rotation control, allowing for pulse lengths up to 5 s. Recent NSTX physics analyses have addressed topics that will allow NSTX-U to achieve the research goals critical to a Fusion Nuclear Science Facility. These...
Dr
Brett Chapman
(USA)
13/10/2014, 14:00
Overview Poster
This overview of results from the MST reversed field pinch program summarizes physics important for the advancement of the RFP as well as for improved understanding of toroidal magnetic confinement in general. Topics include energetic particle effects, 3D helical equilibria, beta and density limit studies, microturbulence, ion heating, and magnetic self-organization physics. With neutral beam...
Mr
Gianluca Pucella
(Italy)
13/10/2014, 14:00
Overview Poster
Since the 2012 IAEA-FEC Conference, FTU operations have been largely devoted to runaway electrons (RE) generation and control, to the exploitation of the 140 GHz EC system and to liquid metal limiter elements. Experiments on RE have shown that the measured threshold electric field is larger than predicted by collisional theory and can be justified considering synchrotron radiation losses. A...
Mr
Francesco Romanelli
(European Commission)
13/10/2014, 14:00
Overview Poster
The European fusion programme is moving into the phase of implementation of its Roadmap. In this context, the JET programme has focused on consolidation of ITER design choices and preparation for ITER operation, with a specific emphasis given to the Bulk Tungsten Melt Experiment that has been crucial for the final decision on the material choice for the day-one tungsten divertor in ITER. In...
Mr
Ge Zhuang
(Huazhong University of Science and Technology)
13/10/2014, 14:00
OV - Overviews
Overview Poster
The experimental research over last two years on the J-TEXT tokamak is summarized, the most significant results including observation of core magnetic and density perturbations associated with sawtooth events and tearing instabilities by a high-performance polarimeter-interferometer (POLARIS), investigation of a rotating helical magnetic field perturbation on tearing modes, studies of resonant...
Ms
Maria Ester Puiatti
(Italy)
13/10/2014, 14:00
OV - Overviews
Overview Poster
The RFX-mod device can be operated both as a Reversed Field Pinch (RFP), where advanced regimes featuring helical shape develop, and as a Tokamak. Due to its flexibility, RFX-mod is contributing to the solution of key issues in the roadmap to ITER and DEMO, including 3D nonlinear MHD modeling, MHD instability control, internal transport barriers, edge transport and turbulence, isotopic effect,...
Mr
Katsumi Ida
(Japan)
13/10/2014, 14:00
Overview Poster
The progress of physics understanding and concurrent parameter extension since the last IAEA-FEC 2012 [1] in the Large Helical Device is overviewed. Recently the plasma with high ion and electron temperature (Ti(0) ~ Te(0) ~ 6keV) is obtained by the combination of 1) a reduction of wall recycling and neutrals by Helium ICRF discharges and 2) optimization of carbon pellet injection and on-axis...
Mr
anatoli Krasilnikov
(Russian Federation)
13/10/2014, 14:00
OV - Overviews
Poster
Russian obligations in the ITER project consist of the development, manufacture, installation and putting into operation at the ITER site of 25 systems. At this stage Institution «Project center ITER» has signed with the ITER Organization 18 procurement arrangements for manufacture and supply of the equipment for ITER. Manufacture of the corresponding systems and development of other 7 systems...
Mr
Hartmut Zohm
(Germany)
13/10/2014, 14:00
Overview Poster
Research on ASDEX Upgrade is programmatically focused on resolving physics questions that are key to the successful operation of ITER as well as informing design choices for a future DEMO reactor. From 2014 on, a significant part of the ASDEX Upgrade programme is run under the EUROfusion MST programme.
Using the flexible set of in-vessel helical perturbation coils, penetration of 3-d fields...
Mr
Vasily Gusev
(Russian Federation)
13/10/2014, 14:00
OV - Overviews
Overview Poster
First experiments on noninductive current drive (CD) using lower hybrid waves at 2.45 GHz are described. Waves were launched by a 10 waveguide grill with 120° phase shift between neighboring waveguides. The experimental conditions for a poloidal slowing-down scheme are described. The CD efficiency is found to be somewhat less than for standard tokamak lower hybrid CD. Geodesic acoustic modes...
Mr
pietro barabaschi
(f4e)
13/10/2014, 14:00
Overview Poster
In 2009, after a complex start-up phase due to the necessity to carry out a re-baselining effort to fit in the original budget while aiming to retain the machine mission, performance, and experimental flexibility, detailed design of the project was begun. In 2012, with the majority of time-critical industrial contracts in place, it was possible to establish a credible time plan, and now the...
Mr
Osamu Motojima
(ITER Organization)
13/10/2014, 14:00
Overview Poster
The ITER Project has visibly made its transition to the construction phase in the two years since the last Fusion Energy Conference in San Diego. By mid-February 2014 commitments to in-kind procurement are approaching 89.6 percentage of the total credit value and 70.7 percentage (99 out of 140) in the number of Procurement Arrangements. Construction is accelerating and the appearance of the...
Mr
Stefano Coda
(Switzerland)
13/10/2014, 14:00
Overview Poster
TCV is acquiring a new 1 MW neutral beam and 2 MW additional third-harmonic ECRH to expand its operational range. Its existing shaping and ECRH launching versatility was amply exploited in an eclectic 2013 campaign. A new high-confinement mode (IN-mode) was found with an edge barrier in density but not in temperature. Density limits close to the Greenwald value were reached – at reduced...
Mr
Joaquín Sánchez
(Spain)
13/10/2014, 14:00
Overview Poster
Recent improvements in TJ-II plasma diagnostics and operation have led to a better understanding of transport, stability and plasma control in fusion plasmas. Impurity transport: Observations of asymmetries in impurity parallel flows in TJ-II ion-root plasmas have been interpreted as an indication of the compressible variation of the impurity flow field and hence of in-surface impurity density...
