Dr
Yasuhiro Suzuki
(National Institute for Fusion Science)
17/10/2014, 08:30
Poster
The reduction of the heat load on divertors caused by Edge Localized Modes (ELMs) is a key issue in the ITER. Large energy flux of Type-I ELMs is expected to cause melting of the tungsten divertors in ITER. One of the methods to control ELMs is an application of Resonant Magnetic Perturbation (RMP) fields; in fact, mitigation or suppression of ELMs by RMPs are observed in many tokamak...
Mr
Guosheng Xu
(China)
17/10/2014, 08:30
Poster
A long-pulse H-mode regime with a record pulse length over 30 s has been achieved in the EAST superconducting tokamak, sustained by RF heating and current drive with advanced lithium wall coating, exhibiting a good global confinement quality with H_98y2 ~ 0.9. The H-mode plasmas are either ELM-free or mixed with irregular small ELMs. A new electrostatic edge coherent mode (ECM) is present...
Dr
Yusuke Kosuga
(Japan)
17/10/2014, 08:30
Poster
A novel theory to describe the formation of shear flow patterns and avalanches by radially propagating heat flux waves is presented. A model for heat avalanche dynamics is extended to include a finite delay time between the instantaneous heat flux and the mean flux, based on an analogy between heat avalanche dynamics and traffic flow dynamics. The response time introduced here is an analogue...
Dr
Ulrich Fischer
(Karlsruhe Institute of Technology (KIT))
17/10/2014, 08:30
Poster
The nuclear design and optimisation of fusion facilities and their components rely on the data provided by neutronic calculations. Suitable computational approaches, tools, and data, qualified and validated for design applications are required to enable reliable design analyses and ensure a sufficient prediction accuracy of the results. Recent efforts aim at extending the capabilities of the...
Dr
Brian LaBombard
(MIT Plasma Science and Fusion Center, USA)
17/10/2014, 08:30
Poster
The MIT Plasma Science and Fusion Center and collaborators are developing a concept for an advanced divertor experimental test facility (ADX) – a tokamak specifically designed to address critical gaps in the world fusion research program on the pathway to DEMO. This high field (6.5 tesla, 1.5 MA), high power density (P/S ~ 1.5 MW/m^2) facility will test innovative divertor concepts for...
Mr
William W. Heidbrink
(USA)
17/10/2014, 08:30
Poster
Experiments on the DIII-D tokamak show that Alfven eigenmode (AE) activity degrades fast-ion confinement in many high β_N, high q_{min}, steady-state scenario discharges. (β_N is the normalized plasma pressure and q_{min} is the minimum value of the safety factor.) An extensive set of diagnostics measure degraded fast-ion confinement: neutron detectors, fast-ion D_α (FIDA) spectrometers,...
Mr
Robert Granetz
(USA)
17/10/2014, 08:30
Poster
Results from an ITPA joint study of the threshold conditions for runaway electron (RE) generation suggest that suppression of RE’s during disruptions on ITER could be less demanding than currently envisioned. In this study of quiescent, non-disrupting discharges, it is found that generating and maintaining measurable RE’s is more difficult than predicted by collisional damping only,...
Dr
Makoto Oyaidzu
(Japan Atomic Energy Agency)
17/10/2014, 08:30
Poster
Since it is predicted from the previous studies that the effects of tritium on corrosion of F82H steel, one of Reduced Activation Ferritic Martensitic Steels, would be higher than that of SUS304 stainless steel, a corrosion behavior of F82H steel in tritiated water circumstance was studied by means of anodic polarization measurements, one of the electrochemical techniques, with changing the...
Dr
Keeman Kim
(Korea, Republic of)
17/10/2014, 08:30
Poster
A DEMO device has been considered the next step following ITER as a near-term prototypical reactor design that is tritium self-sufficient and produces a limited amount of net electricity. The machine maintenance approach and planned configuration concept plays a major role in establishing the design point. DEMO will also need to show that adequate operating availability can be achieved over a...
Mr
Claudio Di Troia
(ENEA)
17/10/2014, 08:30
Poster
A parametric distribution function has been proposed as equilibrium distribution function (EDF) for charged particles in fusion plasmas, representing, e. g. , supra-thermal particle distribution produced by additional external heating sources in tokamak experiments.
This EDF describes an equilibrium because it exclusively depends on constants of motion (COMs). Assuming an axisymmetric...
Dr
Pejman Khorshid
(Dept of Physics, Mashhad Branch, Islamic Azad University, Mashhad, Iran)
17/10/2014, 08:30
Poster
The effect of externally applied resonant helical magnetic fields (RHFs) and a set of saddle coils on plasma column were calculated. The magnetic field of saddle coils compared with magnetic field of the helical winding coil on IR-T1 tokamak in a simulation method. The equation of helical windings that they mounted on vacuum chamber in a spiral modes (L=2, n=1) and (L=3, n=1), where L...
Dr
Wei Chen
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
Shear Alfvén waves (SAWs) are very common in magnetized plasmas both in space and laboratory. In present-day fusion and future burning plasmas, SAWs are easily excited by fast particles and energetic alpha particles produced by nuclear fusion reactions. SAWs can cause the loss and redistribution of energetic particles so that affect plasma performance or damage the plasma wall. The physics of...
Prof.
Maxime Lesur
(Kyushu University)
17/10/2014, 08:30
Poster
A major concern in burning plasmas is that high energy ions can excite plasma instabilities in the frequency range of Alfvén eigenmodes, which significantly enhance their transport. We focus on the Toroidal Alfvén Eigenmode (TAE). In many TAE experiments, the mode frequency is observed to split into two branches that sweep upwardly and downwardly. This nonlinear frequency sweeping (chirping)...
Mr
Lin Nie
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
It is widely accepted that the transient heat flux carried by edge localized mode-filaments (ELM-filaments) can dramatically erode divertor materials, increase impurities and recycling. Thus, it is an extremely challenge to decompose heat flux originating from core plasma. In this paper, the statistical characteristics of ELM-filament within mitigation by the Supersonic Molecular Beam...
Ms
Isabel Maria Nunes
(Portugal)
17/10/2014, 08:30
Poster
As reported in the FEC 2012, operation with a Be/W wall at JET has had an impact on plasma confinement and scenario development relative to the carbon wall. The main differences observed were a degradation of confinement for low betaN scenarios (typically H98~0.8) and W accumulation in the plasma core at low fuelling gas. In order to develop high performance plasmas in DD and ultimately in DT,...
Prof.
Troyo Troev
(Bulgarian Academy of Sciences)
17/10/2014, 08:30
Poster
The interaction of the intensive neutron fluxes with the first wall components of the fusion reactors result on serious structure damages in fusion materials. Atomic displacement cascades induce formation of point defects (i.e. vacancies, interstitial atoms, vacancy and interstitial clusters) and segregation of alloying elements, while nuclear transmutation reactions produce helium and...
Dr
Alexander Spitsyn
(NRC "Kurchatov institute")
17/10/2014, 08:30
Poster
This report will describe conceptual design of the fusion DT fuel cycle for steady-state facility DEMO-FNS project in comparison with fuel cycle for FNS-ST and with engineering design of fuel cycle for T-15 tokamak which is considered as mockup of the fuel cycle without tritium.
Project DEMO-FNS is developed for demonstration of fusion and hybrid technologies and it requires technologies with...
Mr
Keii Gi
(The University of Tokyo)
17/10/2014, 08:30
Poster
A new conceptual design of the 3GW-level, low-magnetic-field, superconducting spherical tokamak (ST) power plant was proposed as an attractive choice for tokamak fusion reactors. We reassessed a possibility of the ST as a power plant using the conservative reactor engineering constraints often used for the conventional tokamak reactor design for the first time. An extensive parameters scan...
Ms
Laila El-Guebaly
(USA)
17/10/2014, 08:30
Poster
A Fusion Nuclear Science Facility (FNSF) could play an important role in the development of fusion energy by providing the nuclear environment needed to develop fusion materials and components. The spherical tokamak (ST) is a leading candidate for an FNSF due to its potentially high neutron wall loading and modular configuration. A key consideration for the choice of FNSF configuration is the...
Prof.
Noriyasu Ohno
(Nagoya University)
17/10/2014, 08:30
Poster
Linear plasma devices (LPDs), sometimes called divertor simulators, bridge the gap between single effect measurements (such as ion beam sputtering measurements, or electron beam high-heat flux tests) and more complicated toroidal plasma confinement facilities. LPDs offer the opportunity to investigate the synergy and coupling between the variety of processes taking place at the interface...
Mr
Jeronimo Garcia
(France)
17/10/2014, 08:30
Poster
Extensive linear and non-linear gyrokinetic simulations, including kinetic electrons, collisions, flow shear, realistic geometry, electromagnetic effects, impurities as well as perpendicular and parallel magnetic fluctuations, and linear MHD analyses performed respectively with the GENE and MISHKA codes, have shown for the first time that the large population of fast ions found in the plasma...
Dr
Yoshiteru Sakamoto
(Japan Atomic Energy Agency)
17/10/2014, 08:30
Poster
Recent development of a DEMO concept with a medium size (major radius of ~8.2 m) and a lower fusion power (~1.5 GW) is presented together with assessment of relevant technologies. The maximum toroidal field is evaluated at ~13 T, which is nearly independent on strand materials (Nb3Sn or Nb3Al) unlike a compact DEMO, while the increase of the allowable design stress has a large impact on that....
Mr
Richard Kemp
(UK)
17/10/2014, 08:30
Poster
To allow coherent conceptual design activities, and later engineering design activities, for a demonstration fusion power plant (DEMO), a self-consistent design point must first be developed. The DEMO design point is a set of parameters characterising the key features of a DEMO power plant on which evaluation of different systems can be based with confidence that there are no significant...
Mr
Bernard Saoutic
(CEA-IRFM)
17/10/2014, 08:30
Poster
Demonstration power plant is the next step for fusion energy following ITER. Key questions remain before a design is selected. Some of these questions can be addressed by simulation through system codes. System codes aim at modeling the whole plant with all its subsystems and identifying their interactions and their impact on the design choice. The SYCOMORE code is a modular system code...
Mr
Keeman Kim
(Korea, Rep. of)
17/10/2014, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Korean Fusion Energy Development Promotion Law (FEDPL) was enacted in 2007 to promote a long-term cooperative fusion research and development among participating industries, universities and research institutes. As a following step, a conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) has been initiated in 2012. The conceptual design activity will continue...
Dr
Kihak IM
(National Fusion Research Institute)
17/10/2014, 08:30
Poster
As a way to realize a large-scale fusion energy, a DEMO device has been considered as a next step after the international ITER device. Pre-conceptual DEMO studies are being carried out by international fusion community including China, EU, Japan and Korea (with participation of US). Early in 2007 in Korea, Fusion Energy Development Promotion Law (FEDPL) was enacted to settle down the legal...
Prof.
Vladimir Sergeev
(Saint-Petersburg State Polytechnical University)
17/10/2014, 08:30
Poster
In this report we discuss key issues of design of the divertor and the first wall of DEMO-FNS. Parameters determining heat loads on the wall and on the divertor targets are similar to those of ITER. Therefore, technologies being developed for ITER project may be partly used in DEMO-FNS design.
As a result of analysis of modern solutions and a simple hybrid modelling, a double null close...
Prof.
Boris Kuteev
(NRC Kurchatov Institute)
17/10/2014, 08:30
Poster
Limited resources of fissile nuclides, disposal of spent nuclear fuel and controlled nuclear fusion are the major system challenges on the path from contemporary to future large-scale Nuclear Energy (NE). Creation of fusion-fission hybrid systems in near-term outlook will definitely ensure success in solving these problems. This will provide involvement of practically unlimited resources of...
Mr
Josef Schweinzer
(Germany)
17/10/2014, 08:30
Poster
In ITER, H-mode operation at 15MA and q=3 is planned to achieve 500MW fusion power at Q=10 in D-T-mixtures. This so-called ITER baseline (BL) scenario is characterized by normalized parameters for plasma density fGW=0.85, energy confinement H=1 and betaN=1.8. A high triangularity shape has been identified to be best suited to combine high density operation with good H-mode confinement....
Dr
Francesco Paolo Orsitto
(Associazione EURATOM-ENEA unita' tecnica fusione)
17/10/2014, 08:30
Poster
This paper reports work done for EFDA PPPT in 2013. It includes the constraints of neutron fluence and Tritium Breeding Ratio(TBR) on diagnostics installation; the technology readiness level of a minimum diagnostics set for control (including burn control);an extended set of diagnostics for control code training; results on diagnostics technology; burn and divertor control. Two DEMO devices...
Mr
Pravesh Dhyani
(Institute for Plasma Research, Gandhinagar, India)
17/10/2014, 08:30
Poster
Improvement in tokamak plasma confinement using biased electrodes observed in many tokamaks is a well-established phenomenon. In this paper we show that very use of the same biased electrode can mitigate the disruptions in tokamak plasmas through stabilization of magnetohydrodynamics (MHD) modes. Disruption induced in Aditya tokamak by H2 gas puffing is successfully mitigated by applying the...
Dr
Jun Cheng
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
It is essential to understand L-H transition mechanisms to provide a predictable power threshold for a successful operation in fusion reactors. Early theoretical and experimental studies have shown that plasma may pass an intermediate phase (I-phase) when the heating power gradually increases, approaching the H-mode power threshold. This extended time scale provides opportunity to study the...
Mr
Tatsuya Kobayashi
(Interdisciplinary Graduate School of Engineering Sciences, Kyushu University)
17/10/2014, 08:30
Poster
This is the first report of the spatiotemporal dynamics of edge plasma during L-H transition, which is based on the direct measurement of radial electric field, density gradient and turbulence intensity in the JFT-2M tokamak. The observations with fine spatial- and time- resolutions provide quantitatively clear views of the L-H transition, which enable us to discuss detailed physical...
Mr
Mario Podesta
(USA)
17/10/2014, 08:30
Poster
Neutral beam injection (NBI) is one of the primary tools foreseen for heating, current drive (CD) and q-profile control in future fusion reactors such as ITER and a Fusion Nuclear Science Facility. However, fast ions from NBI may also provide the drive for energetic particle-driven instabilities (e.g. Alfvénic modes - AEs), which in turn redistribute fast ions in both space and energy, thus...
Mr
Dylan P. Brennan
(USA)
17/10/2014, 08:30
Poster
Recent simulation results have indicated that in experiments with weakly reversed magnetic shear and the minimum in safety factor q just above unity, energetic particles in a slowing down distribution can drive two important MHD modes unstable, one a non-resonant, dominantly 1/1 mode localized within the minimum in q, and the other a resonant, dominantly 2/1 mode, which can cause a disruption...
Dr
Alexander Sivak
(NRC "Kurchatov institute")
17/10/2014, 08:30
Poster
Energetic and crystallographic characteristics of various interstitial configurations of H atoms and their complexes with self-point defects (SIA – self-interstitial atom, vacancy) in bcc Fe have been calculated by molecular statics using Fe-H interatomic interaction potential developed by A. Ramasubramaniam et al. (Phys. Rev. B 79 (2009) 174101) and modified here and Fe-Fe matrix potential...
Dr
Vladimir Pustovitov
(National Research Centre "Kurchatov Institute")
17/10/2014, 08:30
Poster
The paper is devoted to theoretical issues in the problem of plasma stability in the toroidal fusion systems with a resistive wall. The basis of the existing stability theory is the standard energy principle [1] derived within the ideal magnetohydrodynamics (MHD) model. A part of that generally accepted approach is the condition that the Poynting vector vanishes at the plasma-facing surface of...
Dr
Wilfred Anthony Cooper
(Ecole Polytechnique Federale de Lausanne (EPFL), Association Euratom-Suisse, Centre de Recherches en Physique des Plasmas (CRPP))
17/10/2014, 08:30
Poster
A MagnetoHydroDynamic (MHD) equilibrium model to treat plasma rotation approximately in three-dimensional (3D) tokamak geometry with nested flux surfaces is explored. For this purpose, we assume in 3D that the velocity is purely toroidal in (R,phi,Z) cylindrical coordinates. Furthermore, we impose that the toroidal angular rotation frequency is constant on each flux surface. Isothermal...
Dr
Klaus Hallatschek
(Max-Planck-Institute for Plasma Physics)
17/10/2014, 08:30
Poster
We have studied the evolution of the zonal flows (ZF) in first principles two-fluid and gyrokinetic turbulence simulations, while artificially controlling the starting conditions or time dependence of the flows to find the rules governing the flow evolution, the preferred, stable and unstable states, and the influence of inhomogeneities, i.e., the effects of the boundary conditions and of...
Dr
Deliang Yu
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
To study the mechanism of the ELM mitigation by SMBI, a high spatial and temporal resolution charge exchange recombination spectroscopy (CXRS) has been developed. This paper presents the first observation of the evolutions of ion temperature and its gradient in the pedestal measured with CXRS. It is found that the gradient of the ion temperature and the pedestal size both decrease around one...
Prof.
Vladimir Gribkov
(Institute o0f Plasma Physics and Laser Microfusion)
17/10/2014, 08:30
Poster
Samples of materials counted as perspective ones for use in the first-wall and construction elements in fusion reactors (W, Ti, Al, low-activated ferritic steel “Eurofer” and some alloys) were irradiated in the Dense Plasma Focus (DPF) device “Bora” having bank energy of ≤ 5 kJ. The device can generate powerful streams of hot dense (T ~ 1 keV, n ~ 1024 m-3) deuterium plasma streams (v ~ 105...
Dr
Yunbo Dong
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
In tokamak experiments, including JET, JT-60U, Tore Supra, and TEXTOR, it has been shown that the runaway electron (RE) generation occurs usually above a threshold at Bt ≈ 2 T independent on machine size. Recently, disruption mitigation experiments with SMBI and MGI have been carried out in the HL-2A and J-TEXT tokamaks to study various injection scenarios and gas jet penetration. The improved...
Mr
Michael Van Zeeland
(USA)
17/10/2014, 08:30
Poster
Pitch angle and energy resolved measurements as well as wide field-of-view infrared imaging show fast ion losses correlated with applied 3D fields in DIII-D plasmas. In L-mode discharges with slowly rotating n=2 magnetic perturbations, 3D field induced fast ion loss signals from separate scintillator detectors (FILDs), near and well below the plasma midplane, are observed to decay within one...
Dr
Vladimir Moiseenko
(Institute of Plasma Physics of NSC "Kharkiv Institute of Physics and Technology")
17/10/2014, 08:30
Poster
The Uragan-3M device is equipped with two antennas which are fed by RF power with the frequency below ion cyclotron. The frame antenna was used for pre-ionization and the three-half turn (THT) antenna makes plasma heating. Such a regime of heating is briefly described in Ref. 1. In this experimental series, the radial profiles of CV and H-alpha lines intensity and the second cyclotron...
Dr
Linjin Zheng
(University of Texas at Austin)
17/10/2014, 08:30
Poster
Finite Larmor radius effects (FLR) on the low-n MHD modes at high-mode (H-mode) pedestal are investigated in this paper with the inclusion of bootstrap current for equilibrium and rotation effects for stability. When bootstrap current is taken into account, a safety-factor reversal or plateau can be generated at the pedestal. We have shown that the modes of infernal type (or fat interchange...
Dr
Gennady Kulikov
(NRNU MEPhI)
17/10/2014, 08:30
Poster
Technology of controlled thermonuclear fusion (CTF) is traditionally regarded as a practically inexhaustible energy source. However, development, mastering, broad deployment of fast breeder reactors and closure of nuclear fuel cycle (NFC) can also extend fuel base of nuclear power industry (NPI) up to practically unlimited scales. Under these conditions, it seems reasonable to introduce into a...
Dr
Motoki Nakata
(Japan Atomic Energy Agency)
17/10/2014, 08:30
Poster
First-principle based gyrokinetic simulation is a powerful method for investigating turbulent transport in fusion plasmas. Since a local limit condition [(plasma size)/(ion gyroradius) >> 300] is well satisfied in ITER and DEMO reactors, quantitative evaluations for the prediction capability of local gyrokinetic simulations are crucially urgent and important issues.
This paper presents the...
Mr
Marco Valisa
(Italy)
17/10/2014, 08:30
Poster
In the context of the investigations on JET of the effects of an ITER-like wall on the plasma performance, this contribution presents a comprehensive picture of the W transport in the core of JET H-mode plasmas with up to 2.5 MA of plasma current, based on a successful agreement between experiment, interpretative simulations and theoretical predictions. The main outcome is that W is...
Mr
Clive Challis
(UK)
17/10/2014, 08:30
Poster
The replacement of the JET carbon wall (C-wall) by a Be/W ITER-like wall (ILW) has affected plasma confinement by the direct effect of wall materials on key plasma parameters and by the impact of operational techniques necessary to avoid damage to plasma facing components. To investigate the effect of changing wall materials on energy confinement scaling, experiments have been performed with...
Mr
Masaki Osakabe
(Japan)
17/10/2014, 08:30
Poster
Heating of bulk-ions by waves excited by energetic particles, such as fusion born alphas, was theoretically pointed out in the past [1], but none of the experimental results related on this phenomena was reported. This is the first report of experimental results indicating the increases of ion temperatures with Energetic-particle driven Geodesic Acoustic Mode (EGAM) excitation.
On the Large...
Mr
Kenichi Nagaoka
(Japan)
17/10/2014, 08:30
Poster
Study of high-temperature plasma is a key for realizing helical fusion reactor, because helical plasmas have good confinement properties in high density regime and a significant advantage in steady state operation. Recently, after the last IAEA-FEC 2012, discharge scenarios for high-temperature helical plasma have been developed in LHD.
An ion ITB was formed in neutral beam injected (NBI)...
Mr
Mitsuru Honda
(Japan)
17/10/2014, 08:30
Poster
The integrated framework for toroidal momentum transport is developed, which self-consistently calculates the neoclassical toroidal viscosity (NTV), the radial electric field Er and the resultant toroidal rotation together with the scrape-off-layer (SOL) physics-based boundary model. The coupling of TOPICS, VMEC and FORTEC-3D makes it possible to calculate the NTV due to the non-axisymmetric...
Dr
Alexei DNESTROVSKIJ
(Kurchatov Institute)
17/10/2014, 08:30
Poster
The approach to the integrated modelling of plasma regimes in the projected neutron source DEMO-FNS [1] based on different codes is developed. The integrated modelling allows eliminating uncertainties in external parameters for such tasks as plasma current ramp up, steady-state plasma consistency, plasma stability and heat load onto the wall and divertor plates. The following codes are...
Dr
Takuya Goto
(National Institute for Fusion Science)
17/10/2014, 08:30
Poster
Plasma operation control scenario of the LHD-type helical reactor FFHR-d1 was examined using a 1-D calculation code, which calculates temporal evolution of the plasma radial profile by solving a diffusion equation in cylindrical geometry using the model based on LHD experimental results. This study is the first 1-D analysis of the plasma operation control scenario of helical reactors. It was...
Mr
Xiaoquan JI
(China)
17/10/2014, 08:30
Poster
Scaling laws for the prediction of neoclassical tearing modes (NTMs) onset in next generation fusion devices such as ITER have been carried out. However, it is difficult to extrapolate current island width thresholds for the NTM onset to ITER due to the uncertainty physics behind the threshold mechanisms. And some events can also influence the mode onset, such as the large sawtooth period and...
Dr
Maryna Chernyshova
(Institute of Plasma Physics and Laser Microfusion)
17/10/2014, 08:30
Poster
Dense Plasma Focus (DPF) devices PF-6 (6 kJ) and PF-1000 (1.2 MJ) placed at the IPPLM, Warsaw, Poland, are the main facilities that were employed for tests of perspective materials intended for use in future fusion reactors (FR) like Iter and NIF. Their discharge currents reach very high values up to 0.76 MA and almost 3.0 MA correspondingly that are the record figures for the facilities of...
Dr
Jose Helder Severo
(University of Sao Paulo)
17/10/2014, 08:30
Poster
Poloidal and toroidal plasma rotation play an important role on particle and energy confinement and on the stabilization of magnetohydrodynamic instabilities, depending on the rotation intensity.
In the TCABR tokamak, the intrinsic toroidal rotation in ohmic discharges is normally sheared, with counter-current in the core and co-current rotation at plasma edge.
The origin of co-current...
Dr
Yuki HOMMA
(KEIO UNIVERSITY)
17/10/2014, 08:30
Poster
Effects of the classical and neo-classical impurity transport across the magnetic B-field in the Scrape-Off Layer (SOL) of fusion plasmas, have been studied with a new kinetic model using Binary Collision method (BCM). Our model is able to simulate the following two effects, which have been theoretically predicted but neglected in all the existing kinetic impurity transport simulations in the...
Mr
Igor Kirillov
(D.V. Efremov Institute of Electrophysical Apparatus)
17/10/2014, 08:30
Poster
Two blanket concepts were considered and found perspective in Russian design of demonstration thermonuclear reactor DEMO-S (1998-2000): ceramics helium cooled and lithium self-cooled, where lithium is used as tritium breeder and coolant. Indian specialists proposed in 2007 a concept of the lead – lithium ceramic breeder (LLCB) blanket for their DEMO reactor and a test module for International...
Dr
Yipo Zhang
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
Understanding and controlling the confinement of fast ion populations is increasing in importance as we approach self-ignited devices. MHD instabilities in magnetically confined plasmas can often be driven by a population of fast ions. In contrast, these instabilities can often lead to the anomalous loss of fast ions. Therefore, numerous efforts have been dedicated to studying the fast ion...
Prof.
Peter Beyer
(Aix-Marseille University)
17/10/2014, 08:30
Poster
Theoretical understanding of the low to high confinement (L-H) transition in magnetic fusion devices such as ITER still remains unresolved, causing significant uncertainties on the power requirements for entering the H-mode. In particular, turbulence is known to be stabilised by sheared ExB flows, but the mechanism generating the flows in an H-mode is not clearly identified yet.
In this work,...
Prof.
Viacheslav Chernov
(A.A.Bochvar High-technology Research Institute of Inorganic Materials, Moscow, Russia)
17/10/2014, 08:30
Poster
Nanostructured vanadium alloys of V-Me (Cr, W)-Zr-C system have good prospects as structural materials for a new generation of fusion and fission (fast) nuclear power reactors. The required properties of the alloys are achieved by methods of combined heat treatment, including conventional (traditional) thermomechanical treatment (TMT), as for the referenced V-4Ti-4Cr alloys (annealing at 1000...
Mr
Atsushi Ito
(Japan)
17/10/2014, 08:30
Poster
The tungsten nanostructure induced by helium plasma irradiation had been found by the experimental researches for the plasma facing materials in fusion reactors. For the generation of the tungsten nanostructure, it is concerned about the decrease of the maximum allowable heat load and the erosion by arcing on the surface. To clear these problem, we had researched on the formation mechanisms of...
Dr
Ryota Imazawa
(Japan Atomic Energy Agency)
17/10/2014, 08:30
Poster
The authors have proposed a multi-parameter measurement system which identifies current density (j_phi), total plasma current (I_p), electron density (n_e) and electron temperature (T_e) from information of a laser polarimetry and a plasma boundary. This study carries out performance assessment of the multi-parameter measurement and proposes a new equilibrium solver suitable for the...
Mr
Yasushi Todo
(Japan)
17/10/2014, 08:30
Poster
This paper presents the first simulation that predicts both nonlinear saturation amplitude of Alfvén eigenmodes (AE modes) and fast ion transport that are close to measured values in experiment. This simulation enables us to predict the alpha particle distribution and the AE modes activity, which is one of the major concerns for burning plasmas such as ITER. A multi-phase simulation [1], which...
Dr
Andreas Bierwage
(Japan Atomic Energy Agency)
17/10/2014, 08:30
Poster
The dynamics of Alfven waves and fast ions in JT-60U plasmas driven by powerful Negative-ion-based Neutral Beams (N-NB) are studied for the first time using long-time simulations, which include N-NB sources, collisions, MHD and wave-particle interactions self-consistently. The simulations are able to reproduce experimentally observed bursts of MHD activity, which chirp down and up in the...
Ms
Yuan Xu
(Southwestern Institute of Physics, Chengdu 610041 China)
17/10/2014, 08:30
Poster
Extrinsic magnetohydrodynamic (MHD) events such as sawtooth crash, fishbone or edge localized mode (ELM) instabilities are often required to provide the seed islands for triggering neoclassical tearing mode (NTM). However, the spontaneous onset NTM (m/n=3/2) without any detectable extrinsic MHD events has been observed in the HL-2A tokamak. The intrinsic error field is considered as an...
Mr
Akira Hasegawa
(Japan)
17/10/2014, 08:30
Poster
Microstructural data of neutron irradiated W such as size and number density of voids and precipitates obtained by W up to 1.5dpa irradiation in the temperature range of 400-800C were compiled quantitatively. Nucleation and growth process of these defects were clarified and a qualitative prediction of the damage structure development and hardening of W in fusion reactor environments were...
Mr
Rakesh Tanna
(India)
17/10/2014, 08:30
Poster
ADITYA tokamak is engaged in carrying out several dedicated experiments on runaway mitigation, disruption control etc. which are of utmost importance for the successful operation of large size tokamaks, such as ITER. Runaway electron generation and mitigation remains challenging topic in the present tokamak research, as these high-energetic electrons can cause severe damage to the vacuum...
Prof.
Hitoshi Tanaka
(Kyoto University)
17/10/2014, 08:30
Poster
Non-inductive start-up of spherical tokamak (ST) is an important issue to realize compact and economical fusion reactors. In the Low Aspect ratio Torus Experiment (LATE) device, non-inductive start-up and formation of ST by electron Bernstein (EB) waves in a highly overdense regime has been explored. By injection of a 2.45 GHz microwave power of ~60 kW, the plasma current Ip is ramped up to...
Linda Sugiyama
(USA)
17/10/2014, 08:30
Poster
New features [1] of the Quasi Coherent Mode (QCM) have been observed in the EDA H-Regime and our theoretical model indicates that: i) the relevant resistive mode driving factor is the edge sharp plasma pressure gradient; ii) a novel mode topology is involved as the usual “disconnected mode approximation” cannot be applied given that the rotational transform iota(psi)=1/q(psi)=0 on the LCMS...
Dr
Thomas Simonen
(University of California Berkeley)
17/10/2014, 08:30
Poster
Fusion development will require materials capable of withstanding the harsh bombardment of 14 MeV D-T neutron bombardment. The Gas Dynamic Trap (GDT) neutron source concept is aimed to test and qualify suitable materials and sub-components. In this paper we evaluate two ways to further increase the attractiveness of the neutron source suggested by the GDT team.. First is the use of ECH power...
Mr
Xiang Liu
(China)
17/10/2014, 08:30
Poster
Development of materials is an important issue for the future nuclear fusion reactors. In this paper, the developments and main achievements of fusion reactor materials at Southwestern Institute of Physics (SWIP) are overviewed by focusing on the plasma facing materials/components (PFMs/PFCs), structural materials and functional materials. For PFMs/PFCs, an ITER grade high purity tungsten and...
Prof.
Vladimir Gribkov
(Institute of Plasma Physics and Laser Microfusion)
17/10/2014, 08:30
Poster
Dense Plasma Focus device represents a source of powerful streams of penetrating radiations (hot plasma, fast electron and ion beams, X-rays and neutrons) of nanosecond-scale pulse durations. Power flux densities of the radiation types may reach in certain cases the values up to 1013 W/cm2. They are widely used at present time in more than 30 labs in the world in the field of radiation...
Dr
Keeman Kim
(Korea, Republic of)
17/10/2014, 08:30
Poster
With ITER now under construction, increased attention is being paid to the roadmap from ITER to a fusion DEMO, including studies of next-step fusion facilities with nuclear missions. Among these, South Korea’s K-DEMO is unique in its focus on a high toroidal magnetic field, large major radius, steady-state tokamak design for the core of a facility to test fusion nuclear components in Phase I...
Mr
Vinay Menon
(Institute for plasma research)
17/10/2014, 08:30
Poster
SPECTRE is a 0-D physics code developed for Indian DEMO reactors. The code gives a set of operating points based on the ignition criteria and the radial build up is estimated by solving iteratively for the plasma temperaturefor a given fusion power and fusion gain (Q). The ratio of plasma density to Greenwald density is chosen so that the reactor operateswithin density limit while the beta...
Dr
Galina Krashevskaya
(National Research Nuclear University MEPhI)
17/10/2014, 08:30
Poster
It has been found that the plasma confinement by magnetic field of alternating-sign curvature - with convex-concave field lines results in a strong stabilizing action against convective (flute-interchange) perturbations [1]. For simple combinations of mirrors and cusps the calculations give a strongly, centrally peaked stable plasma pressure profiles instead of a shallow ones [1-2].
The...
Dr
Tatyana Sizyuk
(USA)
17/10/2014, 08:30
Poster
Tungsten is the leading high-Z candidate surface material for future tokamak divertor and first wall plasma facing components. There are good reasons for this choice including low activation, high melting point, good thermo-mechanical properties, low sputter erosion, and low tritium retention/co-deposition. However, there are concerns about He, D-T, and neutron-induced microstructure...
Prof.
Kaijun Zhao
(Huazhong University of Science and Technology, China)
17/10/2014, 08:30
Poster
Plasma flows and fluctuations are studied with resonant magnetic perturbations (RMPs) using Langmuir probe arrays on the edge plasmas of the J-TEXT tokamak. The toroidal velocity near the last closed flux surface (LCFS) tends to increase at first with increasing RMP current. When the RMP current reaches 6kA, the toroidal velocities increase (inside the LCFS ) and decease (outside the LCFS)....
Prof.
Vasily Koidan
(NRC "Kurchatov Institute", Moscow, Russia)
17/10/2014, 08:30
Poster
Method of high-level radiation damage production in tungsten have been developed and studied on the facilities of the Kurchatov institute together with high flux plasma effect on the damaged material. The results of the experimental work for the last two years are presented in the paper. Radiation damage from DT neutrons is simulated with surrogate irradiations by high energy ions from...
Mr
Adrianus Sips
(European Commission)
17/10/2014, 08:30
Poster
In recent years, dedicated experiments and coordinated scenario simulations, initiated by the Integrated Operation Scenarios Topical Group of the ITPA, have significantly advanced the preparation of ITER operation. This contribution will review the progress made.
Plasma formation studies report robust plasma breakdown in devices with metal walls over a wide range of conditions, while other...
Dr
Jean-Claude Vallet
(CEA)
17/10/2014, 08:30
Poster
The Broader Approach Agreement (BA) to ITER was signed jointly by Europe and Japan, in February 2007, for a period of ten years. The BA comprises three projects: IFERC, the International Fusion Energy Research Center, including the Computational Simulation Center, CSC, IFMIF-EVEDA, Engineering Design and Validation of a 14MeV neutrons irradiation facility for material testing and STP, the ITER...
Mr
Zhihong Lin
(UC Irvine)
17/10/2014, 08:30
Poster
In the well-accepted and widely-exercised paradigm, the Alfven eigenmode (AE) growth rate can be calculated from a perturbative energetic particle (EP) contribution to a fixed mode structure and real frequency given by MHD properties of thermal plasmas. However, our studies show that accurate prediction of the AE growth rate requires non-perturbative, self-consistent simulations to calculate...
Dr
Sanjay Kulkarni
(Institute for Plasma Research)
17/10/2014, 08:30
Poster
ADITYA is a medium size tokamak with major radius 0.75 m and minor radius of 0.25 m, with toroidal magnetic field up to 1.5 T and has circular plasma in hydrogen gas. The diagnostics used in ICRH experiments are Langmuir probes, visible camera, spectroscopy, soft X-ray and hard X-ray detection techniques, diamagnetic loop, heterodyne on-line density measurements, Thompson scattering, Neutral...
Dr
Pengfei Zheng
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
Vanadium alloys, especially those with the compositions of V-4Cr-4Ti, are attractive materials for fabricating self-cooled liquid lithium blanket in a fusion reactor. However, vanadium alloys are still not considered to be used in near term fusion reactors, because the issues relating to its high temperature deformation, neutron irradiation damage and so on are not sufficiently solved. Thus,...
Dr
Masanori Nunami
(National Institute for Fusion Science)
17/10/2014, 08:30
Poster
A reduced model for turbulent transport driven by micro-instabilities such as ion temperature gradient (ITG) modes is constructed based on nonlinear and linear gyrokinetic plasma turbulence simulations performed under a wide range of conditions for the local plasma parameters and different field configurations of helical systems. It is shown that the ion heat diffusivity has a functional...
Ms
Maiko Yoshida
(Japan)
17/10/2014, 08:30
Poster
Temporal and spatial responses of the electron and ion temperatures (Te and Ti), the electron density (ne), and the toroidal rotation velocity (Vφ) with electron cyclotron heating (ECH) have been clarified for the first time with fast measurements in positive shear (PS) H-mode plasmas, weak shear (WS) plasmas with internal transport barriers (ITBs) and reversed shear (RS) plasmas with ITBs on...
Mr
Cedric Reux
(France)
17/10/2014, 08:30
Poster
Disruptions are a major concern for next generation tokamaks, including ITER. These MHD instabilities lead to the loss of the plasma thermal energy and current on the millisecond timescale. Large electric fields created by the plasma current quench can accelerate several MA of runaway electrons (RE) up to 20 MeV. The influence of the full-metal JET ITER-Like Wall (JET-ILW) on RE is thus a key...
Dr
Zhanhui Wang
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
Plasma fueling with higher efficiency and deeper injection is crucial to enable fusion power performance requirements at high density for next generation devices such as ITER. In BOUT++ code framework, a new module (named trans-neut) has been developed to deal with neutrals and plasmas transport during fueling of supersonic molecular beam injection (SMBI) or gas puffing(GP). It modifies the...
Dr
Pavel Goncharov
(Saint Petersburg State Polytechnical University)
17/10/2014, 08:30
Poster
A tokamak-based source of nuclear fusion neutrons, such as considered in some recent papers and program talks, employs injection of fast atom beams into plasma. Energy spectrum is one of the key characteristics of a neutron source. Distributions of electrically charged fusion products are also important to know since they contribute to plasma heating, if they are confined, and they influence...
Dr
Zhengying Cui
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
Impurity transport in the scrape-off layer (SOL) has been studied for the ohmic heating plasma based on a space-resolved vacuum ultra-violet spectroscopy of which the intensity is absolutely calibrated with bremsstrahlung continuum in the HL-2A divertor tokamak. The radial profiles of carbon emissions of CIII (977 Å: 2s2 1S0-2s2p 1P1) and CIV (1548 Å: 2s 2S-2p 2P) as well as the ratio of CIV...
Dr
Daiji Kato
(National Institute for Fusion Science)
17/10/2014, 08:30
Poster
Tungsten is a prime candidate as divertor material of ITER and DEMO reactors which would be exposed to unprecedentedly high-flux plasmas as well as neutrons. Radiation defects such as vacancies and impurities inherent in the divertor plasmas will play primary roles in enhancement of tritium retention in the tungsten. In this paper, for a better characterization of the radiation damages in the...
Dr
Denis Ivanov
(NRC "Kurchatov Institute")
17/10/2014, 08:30
Poster
The presentation describes the conceptual design of the superconducting magnet (SC) of the fusion neutron source DEMO-TIN that is now under development in Russia and the estimations of the mechanical and electrical loads in it, its shielding, as well as cooling and other performances. The main parameters of that device are as follows: plasma major radius R0 = 2.5 m, minor radius of the plasma...
Prof.
Ambrogio Fasoli
(CRPP-EPFL)
17/10/2014, 08:30
Poster
The TCV tokamak is characterized by the most extreme plasma shaping capability worldwide, the highest microwave EC power concentration in the plasma, and a large degree of flexibility in its heating and control schemes. TCV is presently undergoing major heating upgrades, installing a neutral beam for direct ion heating and increasing the EC power injected in X-mode at the third harmonic (X3)....
Dr
juan knaster
(IFMIF/EVEDA)
17/10/2014, 08:30
Poster
The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Europe and Japan, has accomplished on summer 2013, on schedule, its EDA phase with the release of the engineering design report of IFMIF plant, which is here described, compliant with...
Prof.
Alexander Shimkevich
(NRC “KURCHATOV INSTITUTE”)
17/10/2014, 08:30
Poster
A conceptual facility of tokamak and molten-salt thorium blanket with direct-contacted liquid-metal mass-exchanger which allows uninterrupted extracting protactinium from the blanket and accumulating it in a cascade salt trap separately from fission products.
It is supposed to use only the outer blanken without placing near the central column of the tokamak toroidal coil protection from...
Dr
Ian Jenkins
(CCFE)
17/10/2014, 08:30
Poster
The Tritium Breeding Ratio (TBR) is a critical quantity on DEMO as it will determine the continued availability of one the required fuels and thus strongly affect the viability of the device. The breeding blanket segments will be designed to cover as much of the inside of the vessel as feasible, excepting the divertor region. They must also take account of remote maintainability and allow...
Mr
Alexey Popov
(Russian Federation)
17/10/2014, 08:30
Poster
In the paper the universal scenarios of the low-threshold parametric decay instabilities (PDIs), explaining the anomalous phenomena being already observed [1,2] and potentially important for the energy budget in the future ECRH experiments, are treated.
We investigate the scenario of a low-threshold absorptive PDI [3] based on the parametric excitation of the electron Bernstein wave 3D trapped...
Mr
Alexey Zhirkin
(Russian Federation)
17/10/2014, 08:30
Poster
In this work it is investigated the capabilities of hybrid fusion neutron source (FNS) blankets in reprocessing of spent nuclear fuel and generation of nuclides 233U, 239Pu and tritium. The basic kinds of blankets are considered. There are the blanket with use of heavy water solutions of salts and oxides of uranium and thorium, solid-state and molten salt blanket. The structure and geometrical...
Dr
Defeng Kong
(Institute of Plasma Physics Chinese Academy of Sciences)
17/10/2014, 08:30
Poster
The theoretical and experimental results indicate that the total confinement of the core plasma in a fusion device relies on the structure of pedestal on the edge, and the pedestal turbulence plays an essential role on the pedestal structure. The pedestal turbulence have been studied by using the Langmuir probe arrays on the edge of HL-2A tokamak. The probe arrays were performed about 1cm...
Mr
Min Jiang
(China)
17/10/2014, 08:30
Poster
Recently, a class of distinctive MHD activities before the onset of disruption has been identified on HL-2A density limit and radiation induced disruptive discharges, where the higher radiation level is generally considered as the consequence of high electron density or excessive boundary fueling. This precursor mode is named here according to its phenomenological behavior as the Synchronous...
Dr
Christian Day
(Karlsruhe Institute of Technology)
17/10/2014, 08:30
Poster
The operational window of the divertor in a fusion reactor is mainly given by power handling requirements limited by the material properties, and He ash exhaust requirements limited by the effective pumping speed performance of the divertor vacuum system. Hence, the divertor has to reconcile key physics and technology functions in a sound way. This paper is presenting an integrated assessment...
Dr
Wulu Zhong
(Southwestern Institute of Physics, P.O. Box 432, Chengdu 610041, People’s Republic of China)
17/10/2014, 08:30
Poster
Pedestal behaviors play a key role in determining the global energy confinement of tokamak plasmas, and fusion reaction efficiency of burning plasmas. It is essential to understand the mechanism of the pedestal formation and evolution for optimizing plasma performance and improving accuracy of predictive models. Thus it is important experimentally to track the swift evolution of the pedestal...
Ms
Valerie A. Izzo
(USA)
17/10/2014, 08:30
Poster
Massive gas injection (MGI) is a leading candidate technology for disruption mitigation in ITER, and recent modeling has suggested that MHD modes play a critical role in determining the distribution of radiated power during an MGI shutdown. NIMROD 3D MHD simulations of MGI in both ITER and DIII-D reveal how the distribution of gas jets and the n=1 mode interact to determine the localization of...
Mr
Yuejiang SHI
(Korea, Republic of)
17/10/2014, 08:30
Poster
We report the results of L- and H-mode toroidal rotation experiments in KSTAR. Both NBI and ECH with varying resonance conditions were used for the heating mix and turbulence population control. The experimental results show that ECH causes a counter-current rotation increment both in L- and H-mode plasmas. In the H-mode case, the rotation profiles are flattened by on-axis ECH with a clear...
Dr
Liming Yu
(Southwestern Institute of Physics)
17/10/2014, 08:30
Poster
Fishbone instability not only can lead to loss of energetic particles, but also can trigger other low-frequency MHD modes, such as tearing mode/neoclassical tearing mode (TM/NTM) and the long-lived mode (LLM), then to effect the confinement of the fusion plasma. Meanwhile, the TM/NTM is a very important MHD mode, which can cause serious confinement degeneration and will be the principal limit...
Dr
Mikhail Tsventoukh
(Lebedev Physical Institute RAS)
17/10/2014, 08:30
Poster
Novel approaches for the fusion devices first wall include materials with 'advanced' surface structures. The general idea is the creation of a specific layer (of a micron size) at the first-wall surface. Most promising are - liquid-metal at a capillary-porous structure [1-2], and recently discovered tungsten 'fuzz' structure that consists of metal nanowires [3-5]. The advantages of these...
