Dr
Mark Gilbert
(CCFE)
21/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
Inventory calculations have a key role in designing future fusion power plants because, for a given irradiation field and material, they can predict the time evolution in chemical composition, activation, decay heat, gamma-dose, gas production, and even damage (dpa) dose. For conceptual designs of the European DEMO fusion reactor such calculations can provide information about the neutron...
Dr
Rui Ding
(UsORAU)
21/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Significant advances have recently been made in the understanding of erosion and re-deposition of high-Z plasma facing components in a mixed materials environment, encouraging prospects on control of high-Z material erosion for future reactors. Dedicated DIII-D experiments coupled with modeling reveal that the net erosion rate of high-Z materials is strongly affected by carbon concentration in...
Mr
Sergey Konovalov
(NRC "Kurchatov Institute")
21/10/2016, 08:30
THS - Magnetic Confinement Theory and Modelling: Stability
Poster
Substantial fraction of the plasma current can be converted into runaway electron (RE) current in ITER disruptions. During the RE plateau stage of the disruption the kinetic energy of a runaway beam is expected to be much smaller than the magnetic one. However, at the following current termination phase, the electric field induced due to the RE loss to the wall causes the generation of new and...
Dr
NOBUYUKI AIBA
(Japan Atomic Energy Agency)
21/10/2016, 08:30
THS - Magnetic Confinement Theory and Modelling: Stability
Poster
Diamagnetic MHD equations for plasmas with fast flow were derived for the first time by introducing a suitable ordering parameter to two fluid equations. The extended Frieman-Rotenberg (F-R) equation was obtained from the diamagnetic MHD equations by focusing on impacts of the ion diamagnetic drift effect on ideal MHD stability in rotating plasmas. The MINERVA-DI code was developed to solve...
Dr
Emmanuel Joffrin
(CEA)
21/10/2016, 08:30
EXS - Magnetic Confinement Experiments: Stability
Poster
Disruption remains the major risk for the operation of ITER and fusion reactors. JET is now equipped with three fast disruption mitigation valves (DMVs) located at different poloidal and toroidal locations mimicking the ITER set-up of DMVs. In JET, massive gas injection (MGI) from one DMV is systematically applied with 90% deuterium and 10% Argon when a disruption event is detected for plasma...
Prof.
Gunsu YUN
(Pohang University of Science and Technology)
21/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
Edge-localized modes (ELMs) in the KSTAR tokamak appear substantially different from the conventional picture of ELMs as an explosive transport event in the plasma edge triggered by exponentially growing ballooning and external kink modes on the low field side of the plasma. The 2-D images of ELMs visualized by an advanced imaging diagnostics^1 with microsecond time resolution revealed that...
Dr
Lei Xue
(Southwestern Institute of Physics)
21/10/2016, 08:30
THS - Magnetic Confinement Theory and Modelling: Stability
Poster
The medium-sized copper-conductor tokamak HL-2M, is currently under construction and to be put into operation in the near future. The (up-down) symmetric poloidal field coil system inside the toroidal field coils of the machine has the capability of generating high vertically-elongated plasma. Thus the VDE is an unavoidable issue for HL-2M. Meanwhile, the opposite PF current in the middle of...
Dr
Alessandro Bortolon
(PPPL)
21/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
DIII-D studies of high-frequency ELM pacing by pellet injection were extended to ITER scenarios at low beam torque, demonstrating ELM peak heat flux mitigation with D2 pellets, and also with Li spheres, proving the concept of ELM pacing with non fuel pellets, a technique that could potentially reduce the throughput to the pumping and fuel reprocessing systems in ITER.
Injection of D2 pellets...
Dr
Guosheng Xu
(Institute of Plasma Physics, Chinese Academy of Sciences)
21/10/2016, 08:30
EXD - Magnetic Confinement Experiments: Plasma–material interactions; divertors; limiters; scrape-off layer (SOL)
Poster
A new control technique for the edge-localized modes (ELMs) by pace-making with low-hybrid current drive (LHCD) power modulation has been demonstrated, for the first time, in the EAST superconducting tokamak. The achievable pace-making frequency is up to 120Hz, which appears to be limited only by the pedestal recovery time. LHCD leads to the density pump-out and local flattening of the density...
Dr
Hogun Jhang
(National Fusion Research Institute)
21/10/2016, 08:30
THS - Magnetic Confinement Theory and Modelling: Stability
Poster
We study the role of zonal flows in edge pedestal collapse using a reduced magnetohydrodynamic (MHD) model. A dramatic change of dynamics happens when ideal ballooning modes are stabilized. A detailed analysis shows that a zonal flow driven instability is developed due to a strong excitation of zonal vorticity, resulting in secondary crashes. The presence of subsidiary bursts after a main...
Dr
Shinsuke Fujioka
(Institute of Laser Engineering, Osaka University)
21/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Here we report recent experimental results relevant to the fast ignition (FI) inertial confinement fusion assisted with external kilo-tesla magnetic field. We have experimentally observed generation of 0.6 kT of magnetic field by using laser-driven capacitor-coil scheme, short diffusion time (<< 1 ns) of laser-generated magnetic field into a target material, reduction of the REB beam diameter...
Hans Rinderknecht
(Lawrence Livermore National Laboratory)
21/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Implosions of thin-shell capsules produce strongly-shocked (M > 10), low-density (ρ ~ 1 mg/cc), high-temperature (Ti ~ keV) plasmas, comparable to those produced in the strongly-shocked DT-vapor in inertial confinement fusion (ICF) experiments. A series of thin-glass targets was filled with mixtures of deuterium and Helium-3 gas ranging from 20% to 100% deuterium and imploded on the OMEGA...
Prof.
Akifumi Yogo
(Institute of Laser Engineering, Osasa University)
21/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Fusion fast ignition assisted by laser-driven ion beams requires 10 kJ energy deposition onto the fuel core having ~500 g/cm^3 densities. Assuming 100 kJ as a technically manageable energy of the driving laser, the first milestone can be found on 10% conversion efficiency from the laser energy into ions having kinetic energies of 10-30 MeV/u.
In this paper, we experimentally investigate the...
Prof.
Junji Kawanaka
(Institute of Laser Engineering, Osaka University)
21/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
A new heating laser for fast ignition, called the LFEX-Laser, has been demonstrated with all four beams. The obtained total pulse energy was 2 kJ for a 1 ps pulse duration. The peak power of 2 PW is the highest of all kilojoule lasers in the world and was achieved with a high intensity contrast ratio of 1 × 10^10. To increase the pulse energy to the kilojoule class in a short pulse of 1–2 ps,...
Prof.
Yi Liu
(southwestern institute of physics)
21/10/2016, 08:30
EXS - Magnetic Confinement Experiments: Stability
Poster
Disruption mitigation experiments with MGI have been carried out on HL-2A with a rapid (~1 ms), massive (~1021 particles) injection of helium/neon/argon to study various injection scenarios. The behaviors of runaway currents in MGI induced disruptions have been investigated. A long-lasting RE plateau is achieved after argon injection by MGI even at Bt = 1.28 T, much lower than previous Bt...
Dr
Stanislas Pamela
(CCFE - UKAEA)
21/10/2016, 08:30
THS - Magnetic Confinement Theory and Modelling: Stability
Poster
Future devices like JT-60SA, ITER and DEMO require quantitative predictions of pedestal density and temperature levels, as well as divertor heat fluxes, in order to improve global confinement capabilities while preventing divertor erosion/melting in the planning of future experiments. Such predictions can be obtained from dedicated pedestal models like EPED, and from non-linear MHD codes like...
Dr
Johan Frenje
(Massachusetts Institute of Technology)
21/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Hot-spot ignition planned at the National Ignition Facility (NIF) requires proper assembly of the DT fuel, as manifested by the evolution of areal density (ρR) symmetry and hot-spot ion temperature (Ti). Ideally, a spherically symmetric layer of cold and dense fuel with a ρR exceeding 1 g/cm2 surrounding a ~5 keV lower-density hot spot is obtained at peak convergence. To reach these...
Mr
Zengyu Xu
(Southwestern Institute of Physics)
21/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
After obtaining a full-coverage free curve-surface flow by curve plate with three layer meshes, new experimental results showed that a full-coverage free surface flow can’t be obtained by a flat plate with meshes. More were recently investigated on MHD effects of other free surface flows flowing on flat plate. Base on the experimental data and newly developed modeling method, other way is...
Dr
Anna Widdowson
(UKAEA)
21/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
Post mortem analysis of components removed from the JET ITER-like wall (JET-ILW) provides an overall picture of long term fuel inventory. Results from the first 2011-12 (ILW-1) and second 2013-14 (ILW-2) JET-ILW campaigns are now available making a comprehensive overview possible. Overall plasma times for ILW-1 and ILW-2 are similar: ~ 6 hours limiter plasma and ~14 / ~13 hours divertor...
Dr
Jean-Luc Miquel
(CEA)
21/10/2016, 08:30
IFE - Inertial Fusion Experiments and Theory
Poster
Since the operational commissioning of the Laser Megajoule (LMJ) in October 2014, several experimental campaigns have been achieved, with the first eight beams, and demonstrated LMJ’s aptitudes for the Simulation Program. The Simulation Program of the Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA) combines improvement of physics models, high performance numerical...
Prof.
G. -N. Luo
(CnIPPCAS)
21/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
The first EAST plasma was ignited in 2006 with non-actively-cooled steel plates as plasma-facing materials and components (PFMC) which was then upgraded into full graphite tiles bolted onto water-cooled copper heat sinks in 2008. And the first wall was changed further into TZM in 2012, while keeping graphite for both of the upper and lower divertors. With rapid increase in H&CD power in EAST,...
Dr
roger stoller
(oak ridge national laboratory)
21/10/2016, 08:30
MPT - Materials Physics and Technology
Poster
In addition to the engineering challenges associated with building and operating any complex facility, a range of critical materials issues must be addressed in order to make fusion power commercially viable. These include: (1) developing structural materials with suitably long lifetimes, (2) obtaining a plasma-facing material with sufficient ductility and low tritium retention, and (3)...
Dr
Gergely Papp
(Max Planck Institute for Plasma Physics)
21/10/2016, 08:30
EXS - Magnetic Confinement Experiments: Stability
Poster
Disruptions in tokamaks can lead to the generation of a relativistic runaway electron (RE) beam that may cause serious damage to the first wall. The uncontrolled loss of such a high energy electron beam is intolerable and therefore the issue of how to avoid or mitigate the beam generation is of prime importance for ITER. The European medium sized tokamaks ASDEX Upgrade (AUG) and TCV have...
Mr
nicolas commaux
(oak ridge national laboratory)
21/10/2016, 08:30
EXS - Magnetic Confinement Experiments: Stability
Poster
The shattered pellet injection (SPI) technique has demonstrated disruption thermal quench (TQ) and current quench (CQ) control that scale to meet ITER disruption mitigation requirements. This innovative technique was tested for the last few years on DIII-D and showed improved results when compared to massive gas injection (MGI) technique in comparable conditions. Major disruptions on large...
Yuri Shpanskiy
(NRC "Kurchatov Institute")
21/10/2016, 08:30
FNS - Fusion Nuclear Physics and Technology
Poster
Fusion-fission hybrid facility based on superconducting tokamak DEMO-FNS is developed in Russia for integrated commissioning of steady-state and nuclear fusion technologies at the power level up to 40 MW for fusion and 400 MW for fission reactions. The project status corresponds to transition from conceptual design to engineering one. This facility is considered in RF as the main source of...
