Mr
Thomas Brown
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A toroidal confinement facility study and development of a characteristic experimental device was undertaken to investigate a range of liquid metal divertor and first-wall concepts build on past and expected results from liquid metal experiments: the Lithium Tokamak Experiment (LTX), the National Spherical Torus Experiment Upgrade (NSTX-U), and the Experimental Advanced Superconducting Tokamak...
Dr
Yusuke Shibama
(NATIONAL INSTITUTES FOR QUANTUM AND RADIOLOGICAL SCIENCE AND TECHNOLOGY)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The JT-60SA is a superconducting coil tokamak, which is the project combined with Japanese national project and Japan-EU Satellite Tokamak Programme. The coil system is composed of 18 Toroidal Field (TF) coils, 6 Equilibrium Field (EF) coils and Center Solenoid (CS). The size of the TF coil is 7.5 m high and 4.6 m width. EF coils structures have 12 m in the maximum diameter. Thesse large...
Dr
Alberto Loarte
(ITER Organization)
26/10/2018, 08:30
Poster
The achievement of ITER fusion performance is based upon plasma operational scenarios in which the plasma is in the high confinement regime (H-mode) during the burning phase. The fusion power production level is predicted to strongly depend on the values of the pedestal plasma temperature and density on the inner side of the edge transport barrier (ETB). Similarly, the steep edge density and...
Prof.
laura savoldi
(Dipartimento Energia Politecnico di Torino)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The large Ohmic load (~20 MW/m2) of the wall of the resonant cavity of high-power gyrotrons, designed for tokamaks and stellarators for EC resonance heating and current drive to deliver a microwave power of the order of MW per unit, constitutes one of the major technological limiting factors, despite the small extension of the surface on which it is deposited. Even before reaching the material...
Dr
Holger Reimerdes
(Ecole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), Lausanne, Switzerland)
26/10/2018, 08:30
Poster
The European roadmap for fusion energy has identified plasma exhaust as a major challenge towards the realisation of magnetic confinement fusion. To mitigate the risk that the baseline scenario with a single null divertor (SND) and a high radiation fraction adopted for ITER will not extrapolate to a DEMO reactor, the EUROfusion consortium is assessing potential benefits and engineering...
Dr
Jaehyun Lee
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
The bifurcation of perpendicular rotation ($v_{\perp}$) at the transition of ELM-crash suppression has been measured using electron cyclotron emission imaging (ECEI) system on KSTAR. The ECEI revealed that the ELM crashes are suppressed along with a rapid reduction of $v_{\perp}$, which synchronizes with the transition into and out of the ELM-crash suppression. The $v_{\perp}$ bifurcation is...
Mr
Jae-Sun Park
(Korea Advanced Institute of Science and Technology)
26/10/2018, 08:30
Poster
A divertor detachment experiment in low confinement mode and $B\times \nabla B$ into the divertor was performed in KSTAR to investigate various divertor operation regimes. The low field side (LFS) target parallel particle flux $\Gamma_{\parallel}$ started roll-over first ($n_{e} = 2.0-2.5 \times 10^{19} m^{-3}$), and then the high field side (HFS) target $\Gamma_{\parallel}$ began roll-over at...
Prof.
Tomohiko Asai
(Nihon University)
26/10/2018, 08:30
Poster
The collisional merging experiments of field-reversed configurations (FRCs) at super Alfvénic velocity have been successfully initiated in the FAT-CM device at Nihon University. Drastic increase of the excluded-flux leading to the improved confinement performance of FRC has been observed. This process has an important role to realize FRC based high-beta reactor core to capture high-energy beam...
Dr
Vincenzo PERICOLI RIDOLFINI
(PoIPP)
26/10/2018, 08:30
Poster
The mitigating properties of the divertor advanced magnetic configurations on the target heat load have been analysed with the 2D edge code TECXY for the European DEMO. Particular emphasis is put on the snowflake minus, for which several variants have been proposed just to study this particular effect, where the distance between the two X points, the primary and secondary ones, is varied. In...
Dr
Takuya Goto
(National Institute for Fusion Science)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Conceptual design of a compact LHD-type helical fusion reactor FFHR-c1 has been conducted. This design focuses on a year-long electric power generation with as small a reactor size as possible by adopting the operation with auxiliary heating and innovative ideas for the design of engineering system. This design ensures the path to helical commercial power plants through the examination of...
Mr
Ammar Hakim
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Poster
We describe results obtained from Gkeyll, a full-F continuum
gyrokinetic code, designed to study turbulence in the edge region of
fusion devices. The edge region is computationally very challenging,
requiring robust algorithms that can handle large amplitude
fluctuations and stable interactions with sheath boundary
conditions. Results of turbulence in a scrape-off layer (SOL)...
Dr
Ivan Vargas-Blanco
(Instituto Tecnológico de Costa Rica)
26/10/2018, 08:30
Poster
The small modular SCR-1 Stellarator (R = 247.7 mm, R/a = 6.2, ιa = 0.264) has an ECRH system of 2.45 GHz (5 kW) with an average magnetic field of 41.99 mT [1]. Few studies on conversion of electrostatic Bernstein waves under these conditions have been performed in Stellarators [2,3]. This work presents the results of converting electrostatic Bernstein waves in the SCR-1 Stellarator using the...
Ms
Gayathri V.
(Institute for Plasma Reserch, India)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Efficient design of Tritium Extraction System (TES) for the fuel cycle of any fusion reactor is very important to maintain the tritium breeding ratio and hence sustain the fusion reaction. Hydrogen Isotopes Removal System (HIRS) for Indian Tritium Breeder Blanket removes Q2 (Q = H, D or T) and impurities using Cryogenic Molecular Sieve Bed (CMSB) adsorber at 77K. The CMSB is maintained at...
Mr
bharatkumar doshi
(Institute for plasma research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Steady state super conducting Tokamak (SST-1) is an indigenously built working experimental Tokamak at Institute for Plasma Research (IPR). The primary magnetic configurations and plasma shaping magnetic requirements are provided by Superconducting Magnet Systems (SCMS) comprising of sixteen superconducting D-shaped Toroidal Field (TF) magnets and nine superconducting Poloidal Field (PF)...
Mr
Brijesh Kumar Yadav
(Institute for Plasma Research, Bhat, Gandjinagar, India)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
India is developing the lead–lithium cooled ceramic breeder as the blanket concept to be tested in ITER. In the Indian Lithium cooled Ceramic Breeder (LLCB) Test Blanket Module (TBM), PbLi eutectic alloy is used as multiplier, breeder, and coolant for the CB zones, and Li2TiO3 ceramic breeder (CB) is used as a tritium breeding material. The outer box structure is made of India specific Reduced...
Dr
Dehong Chen
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The liquid lead-lithium (PbLi) blanket concept has become a promising design for fusion DEMO and power plant reactors. To promote the successful application of fusion energy, some R&D; activities on the PbLi blanket have been performed, such as structure material corrosion, thermal hydraulics, magnetic-hydrodynamic (MHD) effect, coolant impurities technology and LOCA/LOFA, etc.. Therefore, it...
Dr
Mattia Siccinio
(EUROfusion Consortium)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In order for the first fusion reactor DEMO to accomplish its mission, it is necessary to identify a plasma scenario which is at the same time performing in terms of fusion power generation and sufficiently stable to ensure the integrity and availability of the machine components for a long time. In the present work, the activities undertaken for this purpose by EUROfusion PMU are...
Mr
Naveen Rastogi
(Institue for Plasma Research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Remote handling (RH) systems are highly challenging for application in the maintenance of fusion devices. The challenges include accurate handling of very heavy payloads using long cantilevered robotic arms with a dexterous manipulator. For the flexibility to execute dynamic tasks safely, these manipulators are typically controlled using a ‘man in the loop’ architecture. Haptic systems with...
Prof.
Yuichi Takase
(University of Tokyo)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The capacitively-coupled combline (CCC) antenna has been developed for current drive by the lower hybrid wave (LHW) on the TST-2 spherical tokamak. In order to excite a highly directional wave required for efficient current drive, an antenna array consisting of many elements is necessary, but it is impractical to feed each of these elements independently in a device with limited accessibility....
Dr
Sergey Ananyev
(NRC "Kurchatov Institute")
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the NRC “Kurchatov Institute” fueling systems (FS) concept for the DEMO-FNS facility incorporating components maintaining plasma parameters, tritium processing and breeding, is being developed. The FS computer model provides calculation functions using the computer code «FC-FNS». It allows to calculate gas flows, tritium inventories and losses in FS for steady-state operation mode.
Within...
Mr
Oliver Crofts
(RACE UKAEA B1 Culham Science Centre, Abingdon, Oxon, UK)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The development of fusion as a viable power source is moving from the science driven design of experimental devices to the engineering design considerations required to develop a feasible power plant. An effective maintenance plan is essential because the time in maintenance is potentially very large.
To be effective a maintenance plan must be outlined early in the plant design because it has...
Prof.
Chijin Xiao
(University of Saskatchewan)
26/10/2018, 08:30
Poster
In a recent experimental campaign in the STOR-M tokamak (*R/a* = 0.46/0.12 cm, *Bt* =0.65 T, *Ip* =22 kA), approximately 100 mg of lithium per load has been evaporated from a heated lithium reservoir and coated on the stainless-steel inner wall to study its effects on the tokamak discharge. The evaporators were designed, developed and supplied by General Fusion Inc.. Although four evaporators...
Prof.
Michiaki Inomoto
(The University of Tokyo)
26/10/2018, 08:30
Poster
Axial merging method is one of the candidates to provide center-solenoid-free start-up of high beta spherical tokamak (ST) plasma, in which two initially formed STs merge through magnetic reconnection in the presence of the guide (toroidal) magnetic field, which is perpendicular to the reconnection (poloidal) magnetic field. Magnetic reconnection between two STs is capable of heating the...
Ms
Neelam Shukla
(IIT Roorkee)
26/10/2018, 08:30
Poster
Tungsten has been planned to be used in the diverter region of International Thermonuclear Experimental Reactor (ITER) as it has the highest heat load capacity, highest melting point and more other favourable physical properties among the metals. Distinct ionic states of tungsten are predicted to be present from divertor to core of the ITER device. Thus, to understand the radiation emissions...
Mr
Juhyeok Jang Jang
(Korea Advanced Institute of Science and Technology)
26/10/2018, 08:30
Poster
Impurity seeding with noble gases, such as krypton (Kr), is regarded as a promising way to mitigate divertor heat loads. In this study, ELMs were successfully suppressed by Kr injection in the KSTAR divertor region and the relation between ELM behaviour and Kr amount was studied in KSTAR plasmas with 0.5 MA plasma current and 2.5 T toroidal field. Figures 1(a)-(c) show the plasma parameters...
Mr
Someswar Dutta
(Institute For Plasma Research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The SST-1 Tokamak has 16 numbers of toroidal field (TF) coils and 9 numbers of super conducting poloidal field (PF) coils. They have been assembled and the in-accuracy in positioning of these coils is measured. The deviations in coil positions will generate error field and this will degrade the plasma performance. The error field produced by the TF coil misalignment can impact the plasma...
Dr
Jayhyun Kim
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
Since 2013 KSTAR campaign, we have investigated the effect of non-axisymmetric (NA) fields on the evolution of magneto-hydrodynamic (MHD) instabilities by using the error field (EF) correction coils. Locking and EF penetration were induced by the torque imbalance between the intrinsic rotation and external magnetic braking. Further increase of the n=1 EF resulted in minor and major...
Prof.
João P. S. Bizarro
(Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, 1049-001 Lisboa, Portugal)
26/10/2018, 08:30
Poster
Exact solutions have been obtained for the conservative part of a standard two-fluid (density plus vorticity) model of the scrape-off layer (SOL) which are of the travelling-wave type and describe transport of large-, machine-scale structures across the plasma cross-section (radially and/or poloidally). These conservative solutions can be of various forms and shapes, either extended or...
Mr
Inwoo Song
(Korea Advanced Institute of Science and Technology (KAIST))
26/10/2018, 08:30
Poster
In fusion plasmas with electron temperature of several keV, most of the tungsten (W) particles are in W27+ to W45+ ionic states, which emit line radiations of a few nm wavelength in the EUV range. Thus, a compact (63x44x18 cm3) advanced EUV spectrometer system (CAES) was recently developed [2] to simultaneously measure spectrally-resolved tungsten emission and spatially-resolved W density...
Dr
YoungMu Jeon
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
Reliable and robust resonant magnetic perturbation (RMP) on the edge-localized-mode (ELM) crash control is crucial for the success of ITER and beyond. In recent KSTAR experiments, a critical dependence of RMP-ELM coupling on the plasma shape was found to be as important as much as $\mathrm{q_{95}}$. In application of the low-n RMP fields, small variations in the lower triangularity by...
Dr
Geert Verdoolaege
(Ghent University)
26/10/2018, 08:30
Poster
We report on an ongoing task within the ITPA concerning a revision of the global H-mode energy confinement scaling in tokamaks, known as IPB98(y,2). The objectives of the task are to update the database with data closer to ITER baseline and hybrid conditions, to expand the parameter range and include new data from devices with reactor-relevant metallic walls, to explore predictor variables and...
Dr
Himank Anand
(ITER Organization)
26/10/2018, 08:30
Poster
A real-time (RT) first wall (FW) heat load control system will be required at a very early stage of ITER plasma operations. The long pulse nature of the device imposes active cooling of all plasma-facing components (PFCs) and thus strict control of surface power flux density at all times. Plasma current ramp-up in limiter configuration on the beryllium FW panels (FWP) is foreseen for all ITER...
Prof.
Jaime Mora-Meléndez
(Instituto Tecnológico de Costa Rica)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The low aspect ratio Spherical Tokamak (ST) MEDUSA (Madison Education Small Aspect Ratio Tokamak) is currently being re-commissioned at the Instituto Tecnológico de Costa Rica, after it was donated by the University of Wisconsin-Madison, USA. The main characteristics of this magnetic confinement device are described as follows: plasma major radius of Ro < 0.14 m, plasma minor radius a < 0.10...
Dr
Hanni Lux
(CCFE, UKAEA)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
During the pre-conceptual design phase of fusion devices such as the European demonstration fusion power plant (DEMO), systems codes provide a fast evaluation of optimal design points and highlight high impact areas. However, determining or evaluating a design point at such an early stage comes with uncertainties in many of the design parameters. These uncertainties are both associated with...
Dr
Richard J. Buttery
(General Atomics)
26/10/2018, 08:30
Poster
A new theory-based integrated modeling of Core, Edge Pedestal, and Scrape-Off-Layer (CESOL) has been developed, validated and used to project core to boundary solutions for an upgrade to DIII-D that will develop the plasma physics path to a steady state fusion reactor. It also represents a significant step towards a whole device modeling (WDM). The simulation reproduces DIII-D high N...
Mr
Jeong-hun Yang
(Seoul National University)
26/10/2018, 08:30
Poster
During the current rise phase of tokamak discharges, evolving current density profiles are associated with the MHD fluctuations that are often held responsible for the confinement degradation, or even disruption, early in the discharge. Moreover, VEST, (Versatile Experiment Spherical Torus) for the NBI heated advanced tokamak regime, adopts the fast current ramp up Ohmic discharge, where the...
Dr
Sang Gon Lee
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
The toroidal rotation from pure ohmic discharges without any external momentum sources is one of the most fundamental types of self-generated intrinsic rotation for magnetic fusion researches. There have been reported a wide range of magnitudes, directions and abrupt reversals for ohmic toroidal rotation studies, no clear physical mechanisms are concluded to explain these intrinsic ohmic...
Dr
Hiroki Hasegawa
(National Institute for Fusion Science)
26/10/2018, 08:30
Poster
The ion inertial effects on the sheath-limited filament dynamics have been investigated with the three-dimensional (3D) electrostatic Particle-in-Cell (PIC) simulations. We have shown that the radial propagation speed of a sheath-limited filament becomes slightly slower in deuterium-tritium (D-T) plasmas than in light hydrogen (H) plasmas because of the gyro motion effect. The filament (blob)...
Dr
Joao Figueiredo
(EuFusionUk and PtIPFN)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
JET upcoming deuterium-tritium campaign, DTE2, is scheduled to take place before the end of 2020. From a point of view of diagnostics developments, for many years JET diagnostics have been upgraded in order to provide adequate support for the scientific exploitation of a D-T campaign, with particular attention to the experimental and operational conditions expected during deuterium-tritium...
Mr
Piyush Prajapati
(Institute for Plasma Research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
As the demand for energy grows, futuristic energy sources like the D-T thermonuclear fusion using the magnetic confinement scheme called tokamak are being researched upon. It is generally presumed that a fusion blanket surrounds the tokamak plasma which absorbs the fusion neutrons, using their energy to convert into heat energy and nuclear transmutation with lithium to re-generate the lost...
Mr
Dikens Christian
(Institute for Plasma Research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
1.3 kW helium refrigerator/liquefier (HRL) system is installed and in operational at Cryogenic division of IPR since 2003. Steady State Super-conducting Tokomak consists of superconducting magnets which are cooled by cryogenic HRL plant. Three numbers of 315 kW asynchronous induction motors are used to drive helium screw compressors of HRL plant, therefore it is very essential to maintain the...
Prof.
Hongli Chen
(University of Science and Technology of China)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
As one of typical blanket concepts for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of helium cooled solid breeder (HCSB) blanket was designed by USTC. Considering that electromagnetic load is one of the main concerns for the blanket module, a FEM (finite element method) model of the HCSB was developed and the electromagnetic analysis of the blanket module was...
John Canik
(Oak Ridge National Laboratory)
26/10/2018, 08:30
Poster
We report on a new simulation capability for predicting plasma-surface interactions, including the evolution of the plasma-facing component (PFC) surface layer that is continually modified by contact with the fusion plasma. This involves a wide range of physical phenomena: our current model includes components for a) the scrape-off layer plasma including fuel ions and extrinsic impurities...
Dr
Vanni Antoni
(Consorzio RFX)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A key component of ITER is the heating Neutral Beam Injector (NBI) system, expected to be the main source of the input power necessary to reach fusion conditions. The nominal parameters of the ITER NBI (40 A negative H-/D- ion beam accelerated to 1 MeV and then neutralized) are so challenging that they require extensive international research and development activities. Reliable operation of...
Ms
shikha Binwal
(Jamia Millia Islamia (A Central University))
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Capacitive coupled plasmas (CCP) have unique applications in microelectronic industries, besides they are also important in plasma interaction with material surfaces, such as near field region of ICRF antenna infusion devices. Systematic studies of these plasmas are concurrently carried in laboratory plasma devices to develop models to explain the anomalous behavior of plasma sheath...
Dr
Suk-Ho Hong
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
KSTAR has been involved in studying leading edge heat loads since 2014 by using series of multi-purpose, brazed W blocks (W-Cu-CuCrZr). They are mounted and assembled into two adjacent, inertially cooled graphite tiles installed in the outer divertor target region of KSTAR, within the field of view of an infra-red (IR) thermography system installed in an upper lateral port and to which special...
Mr
Atul Garg
(Institute for Plasma Research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Current Feeder System (CFS) plays vital role in Superconducting (SC) fusion device, SST-1 (Steady state superconducting Tokamak). As, long pulse operation of the Tokamak and fusion reactors require high magnetic field to confine and shape the plasma, which is fulfilled through the superconducting magnets operating at high current ratings. CFS serves as an interface between the power supply...
Dr
Florian Koechl
(UKAEA)
26/10/2018, 08:30
Poster
The ability to describe the essential physics and technology elements needed to robustly simulate the operation of ITER is critical to being able to model the plasma scenarios that will run in ITER.
The Integrated Modelling & Analysis Suite (IMAS) is used to simulate the 15 MA DT baseline scenario operation, including a description of the plasma evolution from its core up to the plasma facing...
Gerd Gantenbein
(Karlsruhe Institute of Technology)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Within the Work Package Heating and Current Drive (WPHCD), coordinated by the Power Plant Physics and Technology Department of EUROfusion, detailed studies are ongoing, which cover three different systems for plasma heating and current drive. These are, namely, systems using electron cyclotron waves, ion cyclotron waves, and neutral beam injection. The studies are in line with the European...
Mr
Michael Wigram
(University of York)
26/10/2018, 08:30
Poster
A means to handle the extreme power exhaust from tokamak-based fusion power reactors
remains to be demonstrated. Advanced divertor configurations have been proposed as potential solutions, including double-nulls, long-legs and magnetic field flaring with secondary X-points. Modelling of tightly-baffled, long-leg divertor geometries in the divertor test tokamak concept ADX has shown the...
Mr
Bibhu Prasad Sahoo
(Institute for Plasma Research)
26/10/2018, 08:30
Poster
The coupled plasma-neutral transport characteristics in the Scrape-Off Layer (SOL) produced by toroidally discontinuous limiter are essentially 3-dimensional and show strong deviation from the usual uniform SOL approximations. In a recently performed second-phase of EMC3-EIRENE plasma transport simulations for the limiter generated SOL of both original Aditya and Aditya Upgrade configurations,...
Dr
Sun-Ho Kim
(Korea Atomic Energy Research Institute, Daejeon, Korea)
26/10/2018, 08:30
Poster
An efficient heating and current drive in the central or off-axis region of tokamak plasma should be developed for the steady state operation of a tokamak fusion reactor. A fast wave within lower hybrid resonance frequency range(LHFW) could be a scheme for the current drive in a high-density, high-temperature reactor grade plasmas.[1,2] A proof-of-principle experiment was planned for the LHFW...
Mr
Randy Churchill
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Poster
Understanding the physics governing the scrape-off layer is necessary in order to reliably predict machine and operation critical quantities, such as the heat flux width at the divertor, plasma-wall interaction, material migration, effect of divertor condition on the pedestal profile, etc. Among the most basic quantities to predict is how the density and temperature in the SOL change from an...
Ms
Swati Roy
(Institute for Plasma Research, Gandhinagar)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Steady-State Superconducting Tokamak-1 (SST-1) has 16 Toroidal field (TF) and 9 superconducting poloidal field (PF) coils rated for 10 kA DC. TF coils are connected in series and operated in DC condition, whereas PF coils are operated independently in pulse mode. SST-1 current feeder system (CFS) houses 9 pairs of PF superconducting current leads and 1 pair of TF superconducting current leads....
Mr
Kaname Kizu
(National Institutes for Quantum and Radiological Science and Technology)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
To realize JT-60SA of the largest superconducting tokamak device in the world, the current feeder and helium pipes have been designed so as to have the flexible structure with bend and to be supported with octagonal shape. The control system for feeding current and helium has been also developed to operate 18 Toroidal coils, 6 Equilibrium Coils and a Central solenoid. The engineering solutions...
Yuri Shpanskiy
(NRC "Kurchatov Institute")
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Further development of a fusion-fission hybrid facility based on superconducting tokamak DEMO-FNS continues in Russia for integrated commissioning of steady-state and nuclear fusion technologies at the power level up to 40 MW fusion and 400 MW fission reactions. This facility is considered as the main source of technological and nuclear science information in National program for development...
Dr
Louis ZANI
(CEA-IRFM)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The EU DEMO reactor is expected to be among the first applications of fusion for electricity generation in the near future and the design of its magnet system is of central importance as driving power plant performance, budget and production efficiency. In this purpose activities were led by CEA in the framework of EUROfusion to contribute to the EU DEMO magnet system design. It encompassed...
Mr
Gaurang Mahesuria
(Ipr)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Steady state superconducting Tokamak (SST-1) is medium size tokamak, which requires liquid nitrogen (LN2) cooled 80 K bubble shields for reducing direct static heat load from room temperature to superconducting magnets system (SCMS). Dedicated liquid nitrogen booster system has been installed and commissioned to cater 0.7 MPa / 80 K single phase flow for uniform temperature distribution...
Dr
Michael Lehnen
(ITER Organization)
26/10/2018, 08:30
Poster
The disruption mitigation system (DMS) is a key plant system to ensure the reliable and successful operation of ITER from the first experimental campaign onwards. The DMS baseline concept and design is based on present knowledge on disruption mitigation, which, nevertheless, remains subject to significant gaps in understanding, especially as concerns runaway electron (RE) formation and...
Dr
Dmitry Gin
(RuIoffe)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Gamma-spectrometry is used at many nowadays tokamaks due to its ability to provide unique data on fast ions and runaway electrons in hot plasma [1]. Current report dedicated to the Gamma Ray Spectrometer that will operate as a part of the ITER Neutral Particles Analyzer complex – one of the leading diagnostic systems in development progress. Conceptual and Preliminary projects were approved...
Prof.
Eugenio Schuster
(Lehigh University)
26/10/2018, 08:30
Poster
Tight regulation of the burn condition in ITER has been proven possible even under time-dependent variations in the fuel concentration by the use of robustification techniques. One of the most fundamental control problems arising in ITER and future burning-plasma tokamaks is the regulation of the plasma temperature and density to produce a determined amount of fusion power while avoiding...
roberto zanino
(dipartimento energia, politecnico di torino)
26/10/2018, 08:30
Poster
The steady-state power exhaust problem in future fusion reactors (e.g, DEMO) is considered as a major challenge along the path towards fusion electricity. Dedicated work packages are being devoted to this problem within EUROfusion and a dedicated facility (the Italian Divertor Tokamak Test – IDTT) is being designed in Italy. Among the possible solutions for this problem, a liquid metal (LM)...
Dr
Igor Kupriyanov
(A.A. Bochvar High Technology Research Institute of Inorganic Materials (JSC "VNIINM"))
26/10/2018, 08:30
Poster
The first wall panels of the ITER main chamber will be completely armored with beryllium. The primary reasons for the selection of beryllium as an armor material for the ITER first wall are its low Z, high oxygen gettering characteristics and also high thermal conductivity. During plasma operation in the ITER, beryllium besides low cyclic heat loads (normal events) will be suffered by high...
110.
Simulation of cross-separatrix edge plasma transport with the continuum gyrokinetic code COGENT
Dr
Mikhail Dorf
(Lawrence Livermore National Laboratory)
26/10/2018, 08:30
Poster
Axisymmetric (4D) simulations using the finite-volume code COGENT are performed to explore the role of ion kinetic effects in tokamak edge plasmas. The simulation model solves the long wavelength limit of the full-F gyrokinetic equation for ion species coupled to the 2D quasi-neutrality equation for electrostatic potential variations, where a fluid model is used for an electron response. The...
Prof.
Minyou Ye
(School of Nuclear Science and Technology, University of Science and Technology of China)
26/10/2018, 08:30
Poster
It is crucial to exhaust the huge power come from core plasma in future fusion reactor. For a fusion reactor of 1-2 GW fusion power, considering the auxiliary heating power and core radiation, ~200 MW will enter into the scrape-off layer (SOL) and exhausted in the divertor. To find an effective way to exhaust the heat power for future fusion reactor, snowflake divertor (SFD) [D.D. Ryutov,...
Xueqiao Xu
(Lawrence Livermore National Laboratory)
26/10/2018, 08:30
Poster
The BOUT++ code has been used to simulate edge plasma electromagnetic (EM) turbulent transport and to study the role of EM turbulence in setting the scrape-off layer (SOL) widths. More than a dozen tokamak discharges from C-Mod, DIII-D, EAST, ITER, and CFETR have been simulated with encouraging success. The simulation results reproduce the measured pedestal turbulence characteristics and the...
54.
SOL/Divertor Plasma Simulation of Diverging Magnetic Field Configurations for Advanced Divertors
Dr
Satoshi Togo
(Plasma Research Center, JpUTsukuba)
26/10/2018, 08:30
Poster
Handling heat loads onto divertor plates is one of the crucial issues. Advanced divertors expand the flux tube of a divertor plasma and reduce the heat load onto the divertor plate. A Super-X divertor (SXD) sets the outer target plate at a further position in major radius than an ordinary divertor (OD) leading to a largely diverging magnetic field (DMF). In order to simulate supersonic plasma...
Mr
HyunYeong Lee
(Seoul National University)
26/10/2018, 08:30
Poster
Solenoid free start-up scenario is the way to utilize loop voltage from the evolution of equilibrium field using outer PF coils. Also, it can be expected to be as an attractive start-up scheme in the fusion machines with low aspect ratio since flux from external inductance change can be utilized. The solenoid free start-up experiments using outer PF coils have been conducted in various...
Dr
Vipulkumar Tanna
(Institute for Plasma Research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The SST-1 Machine consists of sixteen TF and nine PF superconducting coils. The cryo stable operation of these coils demand the operation temperature of 4.5 K. This technical requirement is met by 1350 W at 4.5 K helium cryogenic system and is operational since 2003. The SST-1 cryogenics systems include, helium as well as nitrogen cryo systems along with its storage, distribution and recovery...
Dr
Young-Seok Park
(Columbia University)
26/10/2018, 08:30
Poster
H-mode plasma operation in KSTAR has surpassed the n = 1 ideal MHD no-wall beta limit computed to occur at beta_N = 2.5 with l_i = 0.7. High beta_N operation produced beta_N of 3.3 sustained for 3 s, limited by tearing instabilities rather than resistive wall modes (RWMs). High fidelity kinetic equilibrium reconstructions have been developed to include Thomson scattering and charge exchange...
Dr
Anders Henry Nielsen
(Technical University of Denmark (DTU), Lyngby, Denmark)
26/10/2018, 08:30
Poster
The Scrape off Layer (SOL) plasma and its coupling with the edge dictate the performance of a discharge to a high degree – especially as all plasma has to go through the SOL, which is the main exhaust channel for the hot plasma. The understanding of the SOL plasma is a key topic in contemporary fusion research.
This contribution provides an overview of the modelling efforts of the plasma...
Dr
Si-Woo Yoon
(National Fusion Research Institute)
26/10/2018, 08:30
Poster
For the realization of the fusion reactor, solving issues for high beta steady-state operation is one of the essential research topics for the present superconducting tokamaks and as a candidate of steady-state scenarios, characteristics of, so called, ‘high beta-poloidal’ discharges[1] is analyzed in depth for the capability of fully non-inductive operation with high bootstrap current...
Dr
Vladimir Minaev
(Ioffe Institute)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Globus-M was a compact spherical tokamak with unique features such as plasma column tightly fitted into the vacuum vessel and high NB heating power density. The toroidal magnetic field in it was limited to 0.5 T. Globus-M2 is an upgraded version of Globus-M machine with substantial increase of engineering parameters (the toroidal magnetic field up to 1 T, the plasma current up to 0.5 MA). The...
Dr
Francesca Poli
(PPPL)
26/10/2018, 08:30
Poster
Following recent characterization of the plasma termination phase from a multi-machine database [1], the ITER termination phase is being analyzed, to define uncertainties due to physics assumptions and to deficiencies in the modeling. Considerable modelling and development has been done on ITER termination scenarios, focussing on specific aspects: magnetic control with transport assumptions...
Dr
Marco Wischmeier
(IPP Garching)
26/10/2018, 08:30
Poster
This contribution presents an overview how research in power and particle exhaust studies relevant to next step devices have advanced our quantitative understanding. For a future fusion reactor, such as the european DEMO, a dissipative power fraction, $f_{diss}$, of $90\%\;-\;97\%$ would simplify the engineering demands on plasma facing components, PFCs. A quantitative understanding of the...
Dr
Devendra Sharma
(Institute for Plasma Research, Bhat, Gandhinagar, India)
26/10/2018, 08:30
Poster
The computational modelling activity of plasma transport in the Scrape-off Layer (SOL) region of Indian tokamaks Aditya and SST-1 has explored a range of aspects of SOL plasma transport in both the devices. While 2-dimensional computations using SOLPS have predictively addressed aspects of the phase-I of divertor plasma operation of the tokamak SST-1, complete 3-dimensional EMC3-EIRENE...
Mr
Aroh Shrivastava
(Institute for Plasma Research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Evaluation of thermal profile inside breeding blanket is an important aspect for fusion reactor. Due to thermal neutron flux during steady state operation of future fusion reactor, breeder materials in the blanket will be at elevated temperature up to 900°C. However, during ITER pulse operation with 1800 s pulse length, the maximum estimated temperature is ~650°C. India specific Reduced...
Mr
Upendra Prasad
(Institute for Plasma Research)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Steady-state Superconducting Tokamak (SST-1) magnet system consists of NbTi/Cu based CICC (Cable-In-Conduit Conductor) wound Toroidal (TF) and Poloidal (PF) coils. The TF coils are wound in double pancakes (DP), whereas the PF coils are in DP as well as layered winding scheme. These coils are cooled down up to 5 K using force flow circulation of helium. The void fraction of helium within the...
Mr
Arvind Tomar
(Institute for plasma research Bhat Gandhinagar India)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Steady-State Superconducting Tokamak-1 (SST-1) has Sixteen Toroidal field (TF) and nine superconducting poloidal field (PF) coils[1]. TF coils are connected in series, whereas, PF coils are to be operated individually in pulse mode. TF coils are operating up to 2.5 T in steady state condition but PF coils have hydraulic as well as heat load issues [2]. In order to operate TF coils and PF coils...
Mr
Jungmin Jo
(Department of Energy Systems Engineering, Seoul National University)
26/10/2018, 08:30
Poster
For the purpose of fusion triton confinement study on KSTAR, square shaped scintillating fiber detector has been installed and tested during the 2017 KSTAR campaign. It is composed of scintillating fiber bundles which are immersed in the lead matrix. Totally 1,056 scintillating fibers whose cross-sectional area is 1 mm^2 are immersed. The scintillation light is detected by Hamamatsu R878...
Mr
Ritesh SUGANDHI
(Institute for Plasma Research, Gandhiangar, India)
26/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Large Volume Plasma Device (LVPD) [1] is a cylindrical shaped, linear device (length=3m,
diameter=2 ) dedicated in carrying out pulsed plasma experiments (tpulse ̃9-50ms )relevant to fusion
and Magnetospheric plasma. In the recent past, investigations are switched from active wave plasma
investigations to understanding of plasma turbulence of whistler and Electron Temperature...
Dr
Raju Khanal
(Tribhuvan University)
26/10/2018, 08:30
Poster
In all bounded plasmas, plasma sheath plays an important role in its stability as well as in determining the particle fluxes and energies reaching the wall. Velocity variation as well as modulation frequency of ions in a magnetized plasma sheath has been studied for different obliqueness as well as strength of the field. Due to sharp gradients of physical parameters in the sheath region fluid...
Dr
Choongseok Chang
(Princeton Plasma Physics Laboratory)
26/10/2018, 08:30
Poster
A serious concern for ITER operation is the ability for the divertor to withstand the steady plasma exhaust heat that will be deposited on the divertor surface along a narrow toroidal strip. A simple, data-based regression from experimental measurements in present devices shows we would have λq≲1mm for ITER operation at Ip=15 MA. However, it is questionable if such a simple extrapolation is...
