Dr
Shwetang Pandya
(India Institute for Plasma Research, Bhat, Gandhinagar, 382-428, India)
24/10/2018, 14:00
Poster
In recent years, the studies of Runaway Electron (RE) generation and energy dynamics in tokamaks have gained great importance from the theoretical and experimental perspective. The generation of high power RE beam during the plasma disruption may damage in-vessel components. Therefore, it is important to study and to suppress the REs for the safe operation of the large size tokamaks, such as...
Mr
Kumar Ajay
(IPR)
24/10/2018, 14:00
Poster
Core-ion temperature measurements are routinely carried out by the energy analysis of passive Charge Exchange (CX) neutrals escaping out of the ADITYA-tokamak (Minor radius a=25 cm, major radius R=75 cm) plasma using a 45-degree parallel plate electrostatic energy analyzer [1]. The temporal evolutions of peak ion temperature in the core regime [typically 80 eV to 120 eV for Aditya circular...
Mr
Amit Kumar Singh
(ITER-India, Institute for Plasma Research)
24/10/2018, 14:00
Poster
In superconducting tokamaks, electric field generated by the central solenoid (CS) for plasma start-up is generally less than that for non-superconducting tokamaks due to the requirement of a robust vacuum vessel and cryostat without insulating break. Moreover, with the CS made of NbTi conductor, there is limitation to maximum dI/dt in the coil to avoid stress limits, resulting in limited loop...
Prof.
Evgenii Gusakov
(Ioffe Institute)
24/10/2018, 14:00
Poster
The extraordinary pump wave two-plasmon decay instability TPDI is analyzed under conditions when only one of the parametrically driven upper hybrid (UH) waves is trapped in the vicinity of the density profile local maximum. It is shown that under these conditions the excitation of absolute TPDI is possible due to a finite width of the microwave pump beam. Its threshold and growth rate are...
Mr
Satyaprasad Akkireddy
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In a nuclear fusion reactor, hot and dense D-T plasma is confined using a combination of magnetic fields in a toroidal shaped vacuum vessel. Interaction of this plasma with the wall materials of vacuum vessel is one of the very important areas of interest as plasma-wall interactions will decide the operational life-time of the reactor in terms of plasma as well as material stability. The...
Dr
Taina Kurki-Suonio
(Aalto University)
24/10/2018, 14:00
Poster
The ITER Pre-Fusion Power Operating (PFPO) phase will include half-field/half-current (2.65T, 7.5 MA) and one-third field (1.8T, 5MA) operating scenarios, which ought to allow H-mode access even with limited heating [1].
While PFPO-1 relies only on ECRH and ICRH to achieve the H-mode, in PFPO-2 also the neutral beams will be applied. In the PFPO phases, the plasma will consist of either...
Mr
Abhishek Sinha
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In a tokamak electron cyclotron emission (ECE) is measured to determine electron temperature profile and its evolution. Michelson interferometer (MI) diagnostic is capable of measuring the spectrum of the ECE in a wide spectral range (70-500 GHz). Usually MI is calibrated with hot-cold technique. The lab calibration of the MI diagnostics is carried out locally with room temperature and cold...
Mr
Pankaj Kumar Srivastava
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Microwave interferometer diagnostic is designed and installed for carrying out chord averaged density measurements for plasma density between $ \sim 5\times 10^{10}-6\times 10^ {11} cm^{-3}$ respectively in the Source and Target plasma regions of Large Volume Plasma Device (LVPD). These regions are developed in LVPD by the introduction of large Electron Energy Filter (EEF). This helped in...
Mr
Gaurav Shukla
(Pandit Deendayal Petroleum University)
24/10/2018, 14:00
Poster
Plasma rotation and its shear in the edge and scrape-off-layer (SOL) region plays an important role in determining overall confinement of tokamak plasmas. The sources of spontaneous generation of these rotations are still not fully understood. Furthermore, to answer the questions like whether they modify the electric field profile or electric field profile modifies the rotation and its shear,...
Mr
Umesh Kumar Nagora
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In a tokamak, an interferometer system measures plasma density using an electromagnetic wave which experiences a phase shift with respect to a reference signal while passing through the plasma column. In millimetre wave spectrum, usually homodyne and heterodyne systems are used to determine phase information. One of the limitations of the homodyne scheme was its inability to differentiate the...
639.
Design and development of Passive Charge Exchange Neutral Particle Analyzer for ADIYA-U Tokamak
Dr
Snehlata Aggarwal
(institute for plasma research)
24/10/2018, 14:00
Poster
Passive charge exchange diagnostic is well established technique for measuring core-ion temperature of tokamak plasma. Energetic neutral particles that are formed due to charge exchange of plasma ions with neutral atoms, can escape from the plasma. These neutral atoms that are re-ionized and analyzed using analyzer can provide information about the energy distribution of plasma ions [1].
A...
Mr
Jagabandhu Kumar
(InIPR)
24/10/2018, 14:00
Poster
A new passive active multijunction antenna (PAM) has been designed and is in advance stages of fabrication for ADITYA-U tokamak. The PAM antenna has the ability to couple lower hybrid waves (LHW’s) in to the plasmas near cut-off densities. The coupling of LHW’s depends on plasma density and its profile near the mouth of the antenna. To determine these plasma parameters, experimentally, an...
Dr
Payal Pandit
(Institute for Plasma Research, Gandhinagar)
24/10/2018, 14:00
Poster
The hydrogen line series is a sensitive diagnostic of detached divertor. Divertor plasma is characterized by low temperature (1-10 eV) and high density (1019~1020 m-3). The three body recombination dominates the divertor region and is highly sensitive to the divertor plasma Te and ne. Based on earlier experiments, NIR (800 nm-2300 nm) spectroscopy system is designed for Aditya-U tokamak since...
Mr
Jayesh Raval
(Institute for Plasma Research (IPR), Bhat, Gandhinagar, India)
24/10/2018, 14:00
Poster
Study of soft x-ray(SXR) radiation emitted during plasma discharge gives valuable informations on magneto hydrodynamic(MHD) activities, e.g. nature of minor and major disruptions, mode structure, magnetic island, plasma shape, plasma position and chord average electron temperature in tokomak. Intensity of SXR radiation depends mainly on electron temperature, plasma density as well as on...
Prof.
Yoshitaka Mori
(The Graduate School for the Creation of New Photonics Industries)
24/10/2018, 14:00
IFE - Inertial Fusion Experiments and Theory
Poster
A laser-driven inertial fusion energy (IFE) reactor should achieve the fusion of injected fuel pellets, which are continuously delivered into the reaction chamber and engaged by laser beams at 10’s Hz. Using a repetitive, 100-fs ultra-intense laser HAMA[1], we have demonstrated the engagement of 1-Hz-injected flying pellets involving fusion neutron reaction for the first time[2]. To induce the...
Dr
Pavel Aleynikov
(Max-Planck-Institut für Plasmaphysik)
24/10/2018, 14:00
Poster
Electron Cyclotron Resonance Heating (ECRH) is the main plasma heating mechanism in Wendelstein 7-X (W7-X) Stellarator. It is provided by 10 gyrotrons at 140 GHz (corresponding to the second harmonic cyclotron resonance at 2.5 T) with the power of 1 MW each. The X- and the O-modes were successfully used in a wide range of operation scenarios: X-mode for low and moderate densities (up to the...
Mr
Tanmay Macwan
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Current distribution inside the tokamak needs to be known for understanding of magnetohydrodynamic (MHD) stability and transport. However, the measurement of radial profile of current density is not easy. The external magnetic measurements yield only the plasma shape and global current profile parameters such as βp and li in tokamaks. The radial current density profile is reconstructed using...
Mr
Lavkesh Lachhvani
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Geodesic Acoustic modes (GAMs), believed to play an important role in L to H transition in tokamaks, are the high frequency branch of the zonal flows and are characterized by toroidally and poloidally symmetric in potential $\phi$ (n=0, m=0) and toroidally symmetric but poloidally asymmetric in density perturbation (n =0, m=1). The coherent modes in the spectral analysis of floating potential...
Ms
Nandini Yadav
(Gujarat University)
24/10/2018, 14:00
Poster
The fuel gas injection(s) in measured quantity during the current flat-top region of Aditya-U tokamak discharges has been observed to modify significantly the edge and scape-off-layer (SOL) plasma properties. The effect of these gas puffs on the neutral temperature and their penetration in the edge and SOL region has been studied by measuring the Hydrogen balmer-emission spectra at 656.28...
Dr
Natsumi Iwata
(Institute of Laser Engineering, Osaka University)
24/10/2018, 14:00
IFE - Inertial Fusion Experiments and Theory
Poster
Laser light with relativistic intensities and pulse length exceeding picosecond (ps) has been available recently. Fast electrons generated by over-ps laser-matter interactions are found to be enhanced beyond the scaling laws used in the sub-ps regime. Theories for sub-ps interactions cannot be scaled up simply to ps regime due to that meso-scale physics such as ion fluid dynamics and multiple...
Dr
LALIT AWASTHI
(IPR)
24/10/2018, 14:00
Poster
Understanding electron transport across magnetic field lines in a fusion device is critical. Linear calculations based on numerical and theoretical models reveal that the ETG mode, which is responsible for the turbulence, is a fast growing instability driven by $\nabla T_e$ with growth rate $\gamma_{ETG}\approx\omega_{*T_e}=k_y\rho_e(c_e/L_{T_e})$, when $\eta_e=L_n/L_T$ exceeds a threshold...
Prof.
Gamal Elaragi
(Egyptian Atomic Energy, Cairo, Egypt)
24/10/2018, 14:00
IFE - Inertial Fusion Experiments and Theory
Poster
In this paper, Egyptian first inertial electrostatic confinement fusion (IECF) device, constructed at the Egyptian Atomic Energy Authority (EAEA-IEC), is introduced the characterization of IEC Plasma Device. It consists of 2.8 cm stainless steel cathode, 6.5 cm anode diameter with 10 cm diameter 30 cm height vacuum chamber. The discharge current and voltage of plasma discharge has been...
Mr
Jay Joshi
(Institute for Plasma Research, India)
24/10/2018, 14:00
Poster
Capacitive discharges are created in the near field regions of ICRF antennas and thus power coupling by these antennas depend on the sheaths around them. Magnetization of ions in the plasma around these antennas also affects the power coupling into the plasma with major implications in ICRF antenna’s in tokomaks.
A capacitive discharge is designed to study power coupling in such plasmas in a...
Dr
Kishore Mishra
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In ADITYA tokamak, ICRF plasma is produced by a single strap poloidal antenna located at LFS by exciting 24.8 MHz with a RF power < 80 kW for the purpose of developing Ion Cyclotron Wall Conditioning (ICWC) scenarios. Suitable combination of density (by regulating RF power and fill pressure) and Bt are investigated to allow the Fast Wave (FW) propagation in the torus volume. Initially at high...
Mr
Narendra Patel
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In Tokamak, the “gas fuelling control” plays an important role to produce plasma in different operation phases from plasma current initiation till end. Apart from main gas injection for plasma initiation, several plasma parameters such as density, temperature, and events like recycling, disruption / runaway mitigation etc. are controlled by injecting the fuel gas in different amount and from...
Dr
Animesh Kuley
(Indian Institute of Science Bangalore)
24/10/2018, 14:00
Poster
We report on nonlinear PIC simulations of wave-wave and wave particle phenomena relevant for RF heating and current drive schemes in tokamaks. For this we have developed a new nonlinear kinetic simulation model based on the global toroidal code GTC. In this model, the ions are considered as fully kinetic particles obeying the Vlasov equation and the electrons are treated as guiding centers...
Prof.
Heinrich Hora
24/10/2018, 14:00
IFE - Inertial Fusion Experiments and Theory
Poster
H-11B Fusion Reactor with Extreme Laser Pulses for non-LTE Igniton
Heinrich Hora
Department of Theoretical Physics, University of New South Wales, Sydney/Australia
h.hora@unsw.edu.au
The progress for the design of a reactor for laser boron fusion is following a road map [1] based on the use of extreme deviations from local thermal equilibrium LTE conditions by using just...
Mrs
RANJANA MANCHANDA
(INSTITUTE FOR PLASMA RESEARCH)
24/10/2018, 14:00
Poster
R. Manchanda1, M. B. Chowdhuri1, Nandini Yadava2, J. Ghosh1, 3, S. Banerjee1, Nilam Nimavat, K. Tahiliani, M. V. Gopalakrishna, U. C. Nagora1, P. K. Atrey1, J. Raval1, Y. S. Joisa1,
K. A. Jadeja1, R. L. Tanna1, and Aditya team
1Institute for Plasma Research, Bhat, Gandhinagar 382 428, India
2Gujarat University, Navrangpura, Ahmedabad 380 009, India
3Homi Bhabha National...
Ms
Rachana Rajpal
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
The first phase operations of Aditya-U successfully performed various plasma experiments with repeatable plasma discharges of maximum plasma current of ~160 kA and discharge duration ~250 ms. The electronics and instrumentation requirement for these experiments are mainly of signal conditioning, embedded digital signal processing and automation. The signal conditioning electronics is...
Dr
Khaled Al-Shboul
(Nuclear Engineering Department, Jordan University of Science & Technology)
24/10/2018, 14:00
IFE - Inertial Fusion Experiments and Theory
Poster
Future inertial fusion reactors are supposed to work with long pulses or with high repetition rates using repeated pellet implosions. In such extreme environments, the reactor wall materials will be disclosed to short X-ray pulses and fusion generated fragments. This will cause ablation to the wall material in the form of plasma that is expected to collide with each other in the center of the...
Mr
Amulya Kumar Sanyasi
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Whistler waves are driven unstable by the runaway electrons generated in tokamak disruptions with serious consequences on reactor scale tokamaks and by relativistic electrons in space plasmas but with different electron distributions. In LVPD, we report observations on whistlers of Quasi Longitudinal (QL) nature. These are highly oblique in nature and have free energy source asssociated with ...
Mr
Janmejay Umeshbhai Buch
(Institute for Plasma Research), Dr
Surya Kumar Pathak
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
The determination of electron density and its fluctuations are essential in understanding the physical principles that determine the confinement in tokamaks. Aditya tokamak at IPR is routinely operated with a peak density of ~ 3 x 1019 m-3 and a typical magnetic field of 0.75T. We present and describe the bench test calibration and its results and the designed FMCW Reflectometer which is...
Mrs
sapna Mishra
(ITER-India,Institute for plasma research)
24/10/2018, 14:00
Poster
The investigation of impurities and its transport study in tokomak plasma play a vital role in determining the overall plasma performance. It is important to understand the transport of impurities in tokamak plasmas in order to control impurity inside the plasma and its deleterious consequences affecting overall plasma performance. In Aditya, strong boron like carbon lines are usually seen in...
Prof.
Boris Kuteev
(National Reserch Center Kurchatov Institute)
24/10/2018, 14:00
IFE - Inertial Fusion Experiments and Theory
Poster
A vital goal of inertial fusion energy (IFE) research is development of high-precision, mass production technologies for cryogenic fuel targets fabrication and their delivery to the reaction chamber at a high rate (10-20 Hz) [1].
At the Lebedev Physical Institute (LPI), a mechanical mockup of IFE reactor has been proposed [2] for developing the reactor-scaled technologies that are...
Dr
JYOTI ATUL
(INSTITUTE FOR PLASMA RESEARCH, GANDHINAGAR, INDIA)
24/10/2018, 14:00
Poster
Mode conversion (MC) process proves to be of prime importance in fusion as well as in magnetospheric plasma [1,2,3]. However, the presence of multiple ion species, even with small concentrations, can lead to the appearance of new and modified resonance, cutoff, and crossover frequencies [4]. Nonlinear effects such as pump self induced filamentation and parametric decays further complicate the...
Mr
Pavel Minashin
(NRC "Kurchatov Institute")
24/10/2018, 14:00
Poster
The T-15-MD tokamak is planned as a normal magnetic-coil tokamak with a flexible ITER-like configuration of the poloidal magnetic field. The main goal of the tokamak T-15-MD is the achievement of long pulse, non-inductive current drive regimes for a high-aspect-ratio divertor plasma configurations.
The simulations of the ECRH and ECCD in T-15-MD tokamak are carried out with the ray-tracing...
Dr
Malay Bikas Chowdhuri
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
Neon impurity injection into the tokamak plasma has been found to improve the plasma confinement, known as Radiative Improved (RI) mode in many tokamaks. It is believed that improved confinement in the RI mode is mostly based on the reduction of growth characteristics of the toroidal ion temperature gradient (ITG) mode due to the increase of Zeff and also because of the suppression of...
Ms
KAJAL SHAH
(PANDIT DEENDAYAL PETROLEUM UNIVERSITY)
24/10/2018, 14:00
Poster
A soft X-ray Crystal spectrometer has been developed to measure toroidal rotation velocity and ion temperature in the core of ADITYA-U Tokamak [1, 2] using Doppler shift and Doppler broadening of helium like argon emission in the x-ray region respectively. The spectrometer uses cylindrically bent Si (111) crystal and two dimension CCD detector to measure resonance spectral line of Ar XVII (1S2...
Dr
Shunsuke Usami
(National Institute for Fusion Science)
24/10/2018, 14:00
Poster
The merging of spherical tokamaks (STs) attract the attention as a candidate of future fusion reactors. In plasma merging experiments of STs, through magnetic reconnection, two torus plasmas are merged into a single torus plasmas with higher beta. In experiments, it is reported that electrons are significantly heated in the vicinity of the X-point, while ions are mainly heated in the...
Mr
Suman Aich
(Scientific officer C)
24/10/2018, 14:00
Poster
In a tokamak, for real-time control of plasma column movement, both horizontal and vertical, accurate measurements of plasma column location is compulsory. Magnetic pick-up coils, measuring induced voltage due to change in flux–linkage to them, are widely used of the measurement of temporal evolution of plasma column position in a tokamak. Although measurements of induced voltages are...
Ms
Abha Kanik
(Research Scholar)
24/10/2018, 14:00
Poster
Laser Heated Emissive Probes (LHEP) have several advantages over conventional filament emissive probes and serve as a tool for direct measurement of plasma potential. Measurement of plasma potential or Electric fields component perpendicular to magnetic field are necessary for fundamental understanding of plasma parameters, transport mechanisms, space charge distribution in plasmas. Owing to...
Dr
Takeshi Watari
(Central Research Laboratory, Hamamatsu Photonics K.K.)
24/10/2018, 14:00
IFE - Inertial Fusion Experiments and Theory
Poster
In the most recent study of inertial confinement fusion, the integration experiments to demonstrate ignition burn are planned using kilojoule to megajoule class laser beam lines in the world. These experiments are based on the “single-shot” experiment of which repetition rate is several-shots per day due to limitations of laser cooling time. A dozen shots every second are required to realize...
Mrs
Kumudni Tahiliani
(Institute for Plasma Research, India)
24/10/2018, 14:00
Poster
Understanding the density limit in a tokamak is very crucial for projecting the fusion grade tokamak machine. An important role in the disruptions for density limit is played by magneto-hydrodynamic (MHD) instabilities associated with the steepening of the current density profile due to the current channel contraction. This shrinkage in the current channel due to increasing densities is...
Dr
Santanu Banerjee
(Institute for Plasma Research)
24/10/2018, 14:00
Poster
In fusion devices, runaway electrons (REs) with energies >=10 MeV, generated predominantly during plasma disruptions, can penetrate through the low-Z first wall and melt the interface of actively cooled parts. Majority of disruptions display MHD modes, as precursors. Radiation cool-off at the edge is seen to trigger abrupt growth of MHD modes, mode locking and thereby disruptions. The REs are...
Mr
Tianyang XIa
(Institute of Plasma Physics, Chinese Academy of Sciences)
24/10/2018, 14:00
Poster
In order to understand and control the heat flux issue for the future tokamaks, the particle and heat fluxes of the EAST RF heating H-mode have been simulated by the 6-field 2-fluid model in BOUT++ framework [1]. The simulated particle fluxes induced by the edge coherent turbulence on the outer divertor targets are comparable with the measurements of the width and peak amplitudes by the...
Mr
Sharvil Patel
(Birla Institute of Technology, Jaipur Campus , India)
24/10/2018, 14:00
Poster
Studies of medium and high Z impurities behavior in high temperature tokamak plasmas have become important considering molybdenum, tungsten are being considered as the first wall materials due to its high melting points and capabilities to handle high heat load. These impurity ions are present due to mainly sputtering processes involving plasma facing components in contact with the edge...
Mr
Hideo Nagatomo
(Osaka University)
24/10/2018, 14:00
IFE - Inertial Fusion Experiments and Theory
Poster
In the fast ignition of laser fusion, a reliable target design is required for an ignition scale target. This paper shows the first optimized target design of an implosion phase of the fast ignition, which is scalable to larger targets.
The fast ignition scheme can be divided into three processes mainly; the formation of highly compressed fuel core plasma, the generation of high-energy...
Dr
Nicola Bertelli
(Princeton Plasma Physics Laboratory)
24/10/2018, 14:00
Poster
The main goal of the NSTX-U is to operate at B=1T. With this magnetic field, the 1st and 2nd harmonics of hydrogen (H) are located at the high-field side and in the core plasma, respectively. As a consequence, part of the high-harmonic fast-wave (HHFW) injected power can be absorbed by the H population. This condition might open up new HHFW scenarios, which in turn can be relevant for the...
Dr
Abhay Ram
(Massachusetts Institute of Technology)
24/10/2018, 14:00
Poster
The practical and economic viability of tokamak fusion reactors depends, in a significant way, on the efficiency of radio frequency (RF) waves to deliver energy and momentum to the plasma in the core of the reactor. Among the various attributes of RF waves is their ability to heat magnetically confined plasmas, induce plasma currents in an effort to achieve steady state, and modify the current...
