Prof.
Gianmaria De Tommasi
(Università degli Studi di Napoli Federico II)
24/10/2018, 08:30
Poster
The JT-60SA is a superconducting tokamak device being built as a joint international project between Japan and Europe in the frame of the broader Approach agreement. One of the main goals of JT-60SA is to study practical and reliable plasma control schemes in view of the power plant. Plasma electromagnetic modelling is one of the essential tools for plasma operation in a fusion device and they...
Mr
AMITKUMAR PATEL
(INSTITUTE FOR PLASMA RESEARCH)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
High temperatures inside tokamak for fusion research is achieved from auxiliary heating systems like neutral beam injectors (NBI), or RF heating devices, viz., ion cyclotron (IC), electron cyclotron and lower hybrid systems where High Voltage Power Supply (HVPS) is an essential requirement. ITER requires 20 MW of ICRF for heating and driving plasma current. A cascaded chain of amplifier is a...
Mr
Juro Yagi
(Institute of Advanced Energy, Kyoto University)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
An advanced molten salt (AMS), in which powders of hydrogen-soluble and chemically reactive metals such as titanium are mixed, is investigated as a potential self-cooled breeding blanket material. It is shown that hydrogen isotope uptake in a vanadium plate in molten salt FLiNaK is suppressed by the addition of Ti powders into the salt. In addition, the corrosion of candidate structural...
Ms
Priti Kanth
(Institute for Plasma Research, HBNI)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Structural materials present in and round any fusion device will face stringent conditions due to the high-energy, high-intensity neutron emitted from the fusion plasma. This will have significant life-limiting impacts on the reactor components of both experimental and commercial fusion devices. The neutrons interact with the material initiating nuclear reaction leading to the production of...
Dr
Lijuan Hao
(Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Super Multi-functional Calculation Program for Nuclear Design and Safety Evaluation, SuperMC, is a full-function neutronics simulation software system including inner-coupled calculations among efficient radiation transport, depletion, activation and shutdown dose. Its advanced capabilities include CAD/image-based accurate modeling for complex irregular geometry, intelligent data analysis...
Mrs
Anita Patel
(Institute For Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Magneto Hydro Dynamic (MHD) phenomena plays an important role in governing liquid metal flow characteristics under strong transverse magnetic field and has, therefore, gained the attention of fusion community for the design of liquid breeder blankets. In presence of plasma confining toroidal magnetic field, the flow of electrically conducting liquid metal (Li/Pb-Li), typically used for coolant...
Mr
Agraj Abhishek
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Structural materials to be used in proposed fusion reactor will be exposed to hostile neutronic environmental conditions. These steels will interact with high energy neutron particles. The interaction is expected to degrade structural material properties such as loss of ductility, increase of yield strength and DBTT temperature. Artificial neural network (ANN) with back-propagation (BPN)...
Prof.
Hiroshi Yamada
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
Energy confinement and thermal transport has been widely regarded as gyro-Bohm in tokamak as well as stellarator-heliotron for a single kind of ion. However, this gyro-Bohm model predicts confinement degradation in deuterium (D) plasmas because of larger normalized gyro radius than in hydrogen (H) plasmas, which conflicts with major experimental observations. This study aims to quantify a...
Ms
Shailja Tiwari
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Neutron Activation System (NAS) is the primary neutron diagnostics for Indian Lead-Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) in ITER. The main objective of NAS is to measure spatial distribution of neutron flux and energy spectra and in-situ measurement of tritium production rate inside the TBM. These measurements will be utilized for validation of neutron transport tools...
Dr
Keii Gi
(Research Institute of Innovative Technology for the Earth)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Paris Agreement requires deep reduction of greenhouse gas emissions. The world is toward rapid transition not only for climate change mitigation but also for sustainable development. Fusion energy has outstanding characteristics of plentiful resources, no nuclear runaway and zero-carbon emission, and its development has made a remarkable progress thanks to large investment for more than 50...
Dr
Masahiro Kobayashi
(JpNIFS)
24/10/2018, 08:30
Poster
Significant core plasma transport improvement is observed in the detachment divertor operation, which is stabilized by application of resonant magnetic perturbation (RMP) to the edge stochastic layer of LHD. Pressure profile becomes peaked and the heat transport coefficient,chi_eff, estimated from transport analysis, reduced in the entire confinement region. The RMP amplitude scan experiments...
Dr
Kiyomasa WATANABE
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
We investigate the penetration threshold of the RMP (Resonant Magnetic Perturbation) by the external coils in the LHD (Large Helical Device) for the various configurations. In a configuration of the LHD, it has qualitative similar dependence with that in Ohmic tokamak plasmas. However, the qualitative dependence on the collisionality is opposite to that in a high plasma aspect configuration,...
Mr
Axat Patel
(Assistant Professor), Mr
Maulik Shah
(Assistant Professor)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
High microwave power is generally measured and characterized by calorimetric dummy loads, which are designed to suit the exiting modes of the gyrotron / HPM. The output mode of the gyrotron is converted to a Gaussian mode-HE11 mode after passing through series of mode converters. The objective of this study is to design and fabrication of Calorimetric Dummy Load with efficient cooling medium...
Dr
Kentaro Ochiai
(QST)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Based on results from the IFMIF/EVEDA project in the Broader Approach (BA) activities, a conceptual design of the Advanced Fusion Neutron Source (A-FNS) in Rokkasho aiming at obtaining material irradiation data up to 20 dpa for a fusion DEMO reactor is presented in this paper. The A-FNS is composed of an accelerator facility with a 40 MeV and 125 mA deuteron beam, a test facility and a post...
Dr
Masayoshi Sugimoto
(JpQSTRFI)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Linear IFMIF Prototype Accelerator aims to operate in Rokkasho Fusion Institute a 125 mA/cw deuteron beam at 9 MeV In order to prove the technical feasibility of the IFMIF accelerators concept.
A 2.45 GHz ECR ion source developed by CEA-Saclay is designed to deliver 140 mA/100 keV CW D + beam. The low energy beam transfer line (LEBT) relies on a dual solenoid focusing system to...
Mr
Yogesh Jain
(Institute for Plasma Research, HBNI)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A Passive Active Multijunction (PAM) antenna is designed and developed and would be commissioned on the ADITYA-U tokamak. The PAM antenna has many advantages over the grill antenna such as exhibiting a lower reflection coefficient at the plasma densities close to its corresponding cut-off density. The PAM antenna along with its transmission line components are designed to deliver RF power up...
Prof.
Jieqiong Jiang
(Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A high intensity D-T fusion neutron generator is an important experimental platform for research and development (R&D) of nuclear energy and nuclear technology applications. High Intensity D-T Fusion Neutron Generator (HINEG) has been developed by the Institute of Nuclear Energy Safety Technology (INEST), Chinese Academy of Sciences (CAS)/FDS team to perform researches on fusion nuclear...
Mr
Sachin S. Chauhan
(Department of Physics, Shri Vaishnav Institute of Technology and Science, Indore, India)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Based on the current trends in thermonuclear fusion research, it is quite likely that future fusion machines, DEMO and beyond, will be operating with tungsten and alloys based on tungsten as the plasma facing material on their walls and targets to dissipate the thermal as well as particle loads under extreme conditions. Tungsten is being preferred because of its superior thermo-mechanical...
Dr
Mukti Ranjan Jana
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Steady state Superconducting Tokamak (SST-1) has a provision for positive hydrogen ion based Neutral Beam Injector (NBI) to raise the tokamak plasma ion temperature ~ 1 keV with neutral hydrogen beam (Ho) power of 0.5 MW at 30 kV. Heart of NBI system is ion extractor system which consists of three grids each made up of OFHC copper. The beamlets originating from the extractor system is focused...
Dr
Hiroyuki Noto
(National Institute for Fusion Science)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The realization of advanced fusion reactors rests with improvement of cooling capacity of divertors. Enhancing mechanical properties of Cu alloys is one of the critical issues for the improvement. This paper reports development of dispersion strengthened Cu alloys using ball-milling, encapsulation, and Hot Isostatic Pressing (HIP) facilities. Cu-Al, Zr and Y alloys have been produced so far....
Dr
Tetsutarou Oishi
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
Stochastization of edge magnetic fields has been extensively studied not only for the ELM mitigation but also for the plasma detachment and the impurity transport. The ergodic layer of Large Helical Device (LHD) consists of stochastic magnetic fields with three-dimensional structure intrinsically formed by helical coils. Reduction of the parallel impurity transport in the ergodic layer, so...
Mrs
Poulami Chakraborty
(Bhabha Atomic Research Centre, India)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the present study, the effect of magnetic field on the corrosion of Indian Reduced Activation Ferritic Martensitic Steel (IN RAFMS) in flowing lead lthium eutectic (Pb-Li) has been studied in an electromagnetic pump driven loop (EMPPIL-M). The corrosion rate in the presence of of 0.5 KG magnetic field at a temperature of 773 K has been found to be 1.3 times higher than that observed in the...
Dr
Takashi Minami
(Institute of Advanced Energy, Kyoto University)
24/10/2018, 08:30
Poster
The effects of magnetic field topology on an electron internal transport barrier (eITB) and on its formation in the helical plasma are discussed in this paper. In helical plasmas, the eITB can be formed by generation of the positive radial electric field with electron cyclotron resonance heating due to the electron-root transition that is related to the neoclassical transport through the...
Mr
Chandra Sekhar Sasmal
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Indigenously developed India specific Reduced Activation Ferritic/Martensitic (IN-RAFM) steels are currently considered as a structural material for the Indian Lead Lithium cooled Ceramic Breeder Test Blanket Module (IN-LLCB TBM). Advanced ferritic/martensitic steels offer the opportunity for improvements in fusion reactor performance, operational lifetime and reliability, superior neutron...
Ms
Ranjana Gangradey
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Vacuum is an inherent part of any Fusion machine. The requirement of providing large pumping speed is growing as fusion science is progressing towards high temperature, high density, and large confinement machines. In its domestic programme of development of technologies for Fusion grade machines, Institute for Plasma research (IPR) developed the sorbent based cryopumps. Using coconut shell...
Prof.
Hitoshi Tanaka
(Kyoto University)
24/10/2018, 08:30
Poster
Electron cyclotron heating and current drive (ECH/ECCD) by electron Bernstein waves (EBWs) with multi-electron cyclotron resonances (ECRs) is carried out by injecting microwaves at two frequencies during the non-inductive start-up of a spherical tokamak (ST) . When the 2nd EBW at 5 GHz is excited in the non-inductively produced ST plasma with the 1st EBW at 2.45 GHz, plasma current is driven...
Dr
Kunihiro Ogawa
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
Study on neoclassical and anomalous transport of energetic particle (EP) in the Large Helical Device (LHD) has been performed by means of escaping EP diagnostics. By starting deuterium operation of the LHD, confinement study of EPs has remarkably progressed by using newly developed comprehensive neutron diagnostics providing the information of EPs confined in the core region. Time evolution of...
Mr
Mayank Rajput
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Displacement per atom (dpa) in fusion reactor materials are essential designing parameters to ensure the reliable functioning and structural integrity of fusion reactor components. All probable reaction channels such as (n,n’), (n,2n), (n,p), (n,α) and (n,d) are open for the interactions of D-T neutrons of 14.1 MeV energy with the fusion reactor material. Evaluation of dpa requires energy...
Dr
Pratipalsinh A. Rayjada
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Er2O3 (erbia) is a leading candidate for hydrogen isotope barrier and electrical insulation coating application in some sub-systems of advanced nuclear fusion research reactor designs. Due to harsh environment of the reactor, structural and microstructural stability of the coatings at elevated temperature is critical. The polymorphs of erbia are reported in cubic, monoclinic and hexagonal...
Mr
Arnab Jyoti Deka
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
ROBIN (RF Operated Beam source in India for Negative Ion research) is a negative H- ion source, which is operational in IPR, Gandhinagar. For measurement of various beam parameters such as beam energy, beam divergence, beam homogeneity and the stripping losses, Doppler Shifted spectroscopy diagnostics was established on ROBIN. The beam properties are studied by varying the source pressure...
Dr
Masaki Nishiura
(The University of Tokyo)
24/10/2018, 08:30
Poster
The dipole plasma exhibits strong heterogeneities in field strength, density, temperature, etc., while maintaining the holistic balance. Enquiring into the internal structures, we reveal the fundamental self-organizing mechanisms operating in their simplest realization (as commonly observed in astronomical systems) [1, 2]. Three new findings are reported from the RT-1 experiment: (i) Creation...
Prof.
Masayoshi Nagata
(University of Hyogo)
24/10/2018, 08:30
Poster
The Spherical Torus (ST) is a leading candidate for an advanced fusion reactor due to its compactness. Transient coaxial helicity injection (T-CHI) is one of CHI schemes, and it is used to generate and ramp-up the plasma current at the initial phase of a discharge. One of the most important issues in T-CHI is whether it can establish a current sufficient for succeeding current drive and...
Mr
Vinit Shukla
(ITER-India, IPR)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the presently available fusion reactors, cryogenic helium is an integral part for cooling the magnets in order to achieve super conductivity. Some of the fusion reactors use tritium as a nuclear fuel along with deuterium, in which a part of tritium is proposed to be breeded through lithium blanket covering the first wall of plasma. Since fusion reactors have very small burn up efficiencies...
Dr
Masayuki Yoshikawa
(University of Tsukuba)
24/10/2018, 08:30
Poster
In the hot ion mode experiments of the tandem mirror GAMMA 10/PDX plasma, the suppression of drift-type fluctuation, which rotate in the direction of the electron diamagnetic drift, has been observed when the axial confinement potential is formed by the electron cyclotron heating (ECH) at the barrier (B) and plug (P) cells. The flute-type fluctuation of which rotation direction is the same as...
Dr
Hiroshi Idei
(Research Institute for Applied Mechanics, Kyushu University)
24/10/2018, 08:30
Poster
A transmission line and a launcher system have been newly developed to conduct the second (2nd) harmonic electron cyclotron (EC) plasma ramp-up with an eXtra-ordinary mode wave in the QUEST spherical tokamak. The incident elliptical polarizations were controlled with two corrugated (quarter/one-eighth wavelength) polarizers. The launcher system with two quasi-optical mirrors produced a sharply...
Mr
Matti Coleman
(CCFE)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The tritium start-up inventory required by a tritium self-sufficient DEMO-class fusion reactor is subject to a wide margin of uncertainty, with estimates in the literature varying from less than 1 kg to almost 20 kg for a ~2 GW fusion reactor. If ITER is successful, it is conceivable that multiple DEMO-class devices may be developed in parallel; the European DEMO machine, the Chinese Fusion...
Dr
Hiroshi Tanabe
(University of Tokyo)
24/10/2018, 08:30
Poster
We present the latest results of high-resolution 2D imaging measurement of merging/reconnection heating during the central solenoid (CS)-free plasma startup of spherical tokamak using a new 96CH 2D ion Doppler tomography diagnostics. In the last decade, magnetic reconnection research made a major progress such as (a) achievement of $\sim$1keV plasma heating in MAST both for ions and electrons,...
Dr
Yasuhiro Suzuki
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
A topological change of the magnetic field structure on a transition phenomenon is investigated in the Large Helical Device (LHD). In the high-beta plasma experiment of the LHD, the spontaneous transition phenomenon is sometimes observed [1]. After the transition, the plasma density is increased and then the plasma stored energy is increased. One important observation after the transition is...
Dr
Asha Attri
(ITER-India, IPR)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ion-solid interaction has fundamental importance and is a subject of evolving understanding for years. Energetic ions of energies eV to MeV are responsible for the kinetics in solids by transferring energy via elastic or inelastic interaction depending on the nature of the material. Tungsten is prime material to be used in future fusion devices because of its thermal and mechanical...
Dr
Kenji Tanaka
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
The positive isotope effects have been found in ECRH plasma of LHD. The enhancement factor of global energy confinement time (tauE) to ISS04 scaling in deuterium (D) plasma is about 17% better than in hydrogen (H) plasma. Ion scale density fluctuation level is higher in D plasma. Core fluctuation level in D decreases rapidly with increase of tauE.
Both tokamak scaling (ITER98y2) and...
Both tokamak scaling (ITER98y2) and...
Mr
Rameshkumar Joshi
(Institute for Plasma Research, India)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Lower Hybrid Current Drive (LHCD) system has four klystrons, each rated for 0.5 MW, CW power at 3.7 GHz, which are employed to launch the lower hybrid waves into plasma [1]. VME and PXI based Data Acquisition and Control (DAC) system has already been implemented for the operation of LHCD System. VME based DAC system has been modified to incorporate measurement of RF Power signals.
The...
Mr
Žiga Štancar
(Jožef Stefan Institute)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The work presented in the paper is focused on the development of a multiphysics methodology for the creation of a realistic plasma neutron source for Monte Carlo neutron transport calculations. We begin with a description of the plasma neutron sources used in fusion neutronics so far – these are based on the assumption that the plasma is in thermal equilibrium, the neutrons being emitted...
Dr
Kensaku Kamiya
(QST, Naka)
24/10/2018, 08:30
Poster
Multiple turbulent plasma states in the edge transport barriers (ETBs) formation are studied on JT-60U. Following a slow transition, which causes significant reduction in the ion thermal transport in the pedestal towards the neoclassical level with a weak negative Er value, we found a clear and fast changes in the particle transport in association with the change in the Er towards a strong...
Dr
Makoto Kobayashi
(National Institute for Fusion Science)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the Large Helical Device, deuterium plasma experiments began in March 2017 and completed in August 2017. In this experimental campaign, about $4×10^{18}$ neurons were generated and activated components in the torus hall. The concentration of radioactive isotopes in the components in the torus hall must be evaluated to estimate the radiation dose for workers and to plan the decommissioning...
Dr
Sejal Shah
(ITER-India, Institute for Plasma Research, Bhat, Gandhinagar, India)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Neutron Irradiation impact on ITER grade insulating material
Sejal Shah1,4a, Sunil Kumar2, Sudhirsinh Vala2,4, R. Kumar2, M. Abhangi2, S. Prasad3, M. Bandyopadhyay1,4, A. Chakraborty1
1. ITER-India, Institute for Plasma Research, Bhat, Gandhinagar- 382428, India
2. Institute for Plasma Research, Bhat, Gandhinagar-382428, India
3. FCIPT Division, Institute for Plasma Research, Bhat,...
Mr
Gediminas Stankunas
(Lithuanian Energy Institute)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
IFMIF-DONES (International Fusion Materials Irradiation Facility – DEMO-Oriented Neutron Source) is an accelerator based d-Li neutron source which aims at the qualification of materials at the irradiation conditions of a DEMO fusion power reactor as being developed in the frame of EUROfusion’s Power Plant and Technology (PPPT) programme. The high intense neutron radiation produced in the...
Mr
H. L. SWAMI
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The testing of the breeding blanket systems is one of the vital objectives of the ITER. It will generate the significant information for DEMO fusion reactor. ITER has assigned the three equatorial ports for testing of six blanket systems. In those six, there is a Test Blanket System (TBS) of India which is Lead Lithium Ceramic Breeder (LLCB) blanket system and it will be integrated into...
Dr
Gen Motojima
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
Superior control of particle recycling and of plasma density has been established in the Large Helical Device (LHD) using greatly enhanced active pumping of the closed helical divertor (CHD). In-vessel cryo-sorption pumping systems inside the CHD in five out of ten inner toroidal divertor sections have been developed and installed step by step in LHD. The total effective pumping speed obtained...
Mr
Colin Walters
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The UK Government has invested ~€100M to create two new UKAEA centres for fusion research –
Hydrogen-3 Advanced Technology (H3AT) and the Fusion Technology Facilities (FTF) both opening in
2020-21. FTF and H3AT will foster close cooperation with industry, academia and other international
laboratories to develop and transfer knowledge between partners, offering opportunities to ...
Mr
Kumarpalsinh Jadeja
(Institute for plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In ADITYA Upgrade, glow discharge wall conditioning (GDC) is performed for long hours after the tokamak plasma operation using H gas to control Oxygen and Carbon containing impurities. This leads to high retention of H gas on Graphite limiter and Stainless Steel (SS) vessel. Subsequently, high H outgassing rate requires increased pumping time and high H recycling during plasma discharges...
Dr
Elina Pajuste
(University of Latvia)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Novel method for determining the depth profile of tritium in metallic samples has been demonstrated. Tritium accumulation in the fusion reactor materials is considered as a radiological issue due to its radioactivity. Therefore, tritium behavior prediction and estimation of its overall retention in fusion devices is of high importance.
Proposed method in this study allows to measure depth...
Dr
Dobromir Panayotov
(FUSION FOR ENERGY)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Safety studies for fusion facilities are commonly conducted using codes originally developed for fission reactor accident analysis and adapted to model the fusion-relevant phenomena. Nevertheless there are many “fission developed” methods still not considered in fusion safety assessment which could offer significant advantages in the fusion power commercialization. Along with solving the...
Dr
Stefan Gerhardt
(Princeton Plasma Physics Laboratory)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The NSTX-U device began operation in 2016, producing 10 weeks of commissioning and scientific operations. However, a number of technical issues, including the failure of a key diverter coil, resulted in the suspension of operations. A comprehensive extent of condition review was initiated at the request of the Department of Energy; this paper will summarize the result of that process,...
Prof.
Kazuaki Hanada
(Advanced Fusion Research Center, Research Institute for Applied Mechanics, Kyushu University)
24/10/2018, 08:30
Poster
Out-flux of fuel particles from plasma-facing walls (PFWs) during long duration discharges on all-metal PFW QUEST is in agreement with a prediction of the hydrogen (H) barrier model we proposed [1]. A simple calculation based on the combination of rate equations of H state and the H barrier model predicts a significant impact in the response of plasma density. This result indicates that a...
Dr
Jyoti Shankar Mishra
(Institue for plasma research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
High density plasma operation with centrally peaked profile is one of the key aspects in achieving break-even condition in magnetically confined fusion devices. In this prospect an efficient fuelling method capable of supplying particles into the core of the plasma is desired. Till date, cryogenically solidified pellets of hydrogen isotopes have been proved as an efficient method of...
Mr
SUDHIRSINH VALA
(INSTIUTE FOR PLASMA RESEARCH)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Fusion Neutronics laboratory at Institute for Plasma Research (IPR), Gandhinagar, India has indigenously developed an accelerator based 14-MeV neutron generator for fusion neutronics studies for material development under Indian Fusion program. This neutron generator is producing neutron yield of $10^{10}$ n/s and it will be further upgraded to the $10^{12}$ n/s. It consists of a 2.45 GHz...
Ms
Pujita Bhatt
(Senior Research Fellow)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In high microwave power applications like gyrotron, transmission line system, calorimetric dummy load, etc, requires design, modeling, simulation and evaluation of transmission line system before fabrication of the same is undertaken. Under the aegis of Department of Science and Technology (DST), a multi-institutional program for the development of a gyrotron operating at 42±0.2GHz/200kW/3secs...
Dr
Akira Ejiri
(Graduate School of Frontier Sciences, The University of Tokyo)
24/10/2018, 08:30
Poster
Plasma current start-up without a large flux swing by the central solenoid is a critical issue in fusion research. The lower hybrid wave (LHW) is known to be an effective current drive tool in conventional tokamaks, and it is used in the TST-2 spherical tokamak (ST) device. The TST-2 device provides a unique opportunity to compare outboard-launch and top-launch schemes for plasma current...
Prof.
Viacheslav Chernov
(A.A.Bochvar High-technology Research Institute of Inorganic Materials (SC "VNIINM"))
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The structure and physical-mechanical properties of the metal structural materials (SM) with BCC (ferrite-martensitic steels, alloys of vanadium, etc.) and FCC (austenitic steels, etc.) crystal lattices in the conditions of “before-after-during” low-temperature irradiation were analyzed. The qualitative and quantitative distinctions of the states and properties of SM “before-after” (an...
Dr
Tokihiko Tokuzawa
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
We report the discovery of rapid momentum change and oscillatory flow as a result of the pellet injection. Novel diagnostics tools with high spatio-temporal resolution applied to the perpendicular flow velocity and turbulence intensity measurements in LHD experiments show the following results. Just after the pellet injection, (1)the damped oscillating flow velocity and the increasing density...
Mr
ROHIT KUMAR
(Institute For Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The ADITYA-U tokamak (R0 = 0.75 m, a = 0.25 m) is designed to have shaped plasmas in both single and double null diverter configurations. It is quite well known that sustaining a shaped plasma in tokamak requires very good plasma column position control, both horizontal and vertical. A proportional–integral–derivative (PID) based control system has been designed and operated to achieve...
Prof.
Yonghua Ding
(International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics (IFPP), AEET, SEEE, CnHUST)
24/10/2018, 08:30
Poster
Controlling the tearing mode (TM) is one of the major topics of fusion research, since TM degrades the plasma confinement and even induces major disruption if it is locked. Previous experimental and theoretical studies showed that the resonant magnetic perturbations (RMPs) influence both the rotation and width of the TM. As a result, the static RMP could apply a net stabilizing and braking...
Mr
ArunPrakash Arumugam
(Institute for Plasma Research, Bhat, Gandhinagar, India)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Steady state Superconducting Tokamak (SST-1) is a large aspect ratio Tokamak with a major radius of 1.1 m and minor radius of 0.20 m. Plasma Facing Components (PFC) is one of the major sub-systems of SST-1 Tokamak. Plasma Facing Components of SST-1 consists of divertors, passive stabilizers, baffles and poloidal limiters. PFCs are designed and fabricated to be Ultra High Vacuum (UHV)...
Dr
Takuma Wakatsuki
(National Institutes for Quantum and Radiological Science and Technology)
24/10/2018, 08:30
Poster
Safety factor profile control via active feedback control of electron temperature profile during a plasma current ramp-up phase of a DEMO reactor is investigated to minimize the magnetic flux consumption of a central solenoid (CS) for wide range of *q* profiles. It is shown that *q* profiles with positive, weak and reversed magnetic shear can be obtained with less than half of the empirical...
Prof.
Yasushi Ono
(University of Tokyo)
24/10/2018, 08:30
Poster
The high-power reconnection heating of ST plasma has been developed in TS-3U, TS-4U and MAST experiments, leading us to direct access to burning plasma. This unique method is caused by the promising scaling of ion heating energy that increases with squire of reconnecting magnetic field B_rec. We studied mechanisms for this B_rec^2-scaling of reconnection (ion) heating mainly using TS-3U...
Dr
Arakcheev Aleksey
(Budker INP)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Experiments simulating the pulsed heat loads expected in the ITER divertor were carried out at the BETA facility in the Budker Institute. Using a pulsed electron beam with a duration of 0.2-0.3 ms and heat load with a heat flux factor HFF ≈ 30 MJ m-2s-0.5 below the melting point of tungsten were obtained. A distinctive feature of BETA is the ability to study the processes of erosion of...
Mr
Kunal Bhatt
(ITER-India, Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
ITER cooling waters system consists of large piping network to remove the heat load of about 950MWatt through various branched connections. Many of the branches are connected to main pipes by half coupling full penetration weld joints. There is requirement is to have full penetration for all the joints however quality classification (QC-2), recommends only 10% testing of the total weldment. In...
Dr
Shyamkumar Khambholja
(B & B Institute of Technology, Vallabh Vidyanagar, Gujarat, India)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Lead-Lithium (Pb-Li) alloy in its eutectic composition is one of the promising candidates to be used as liquid blanket in fusion reactor. Helium cooled Lead Lithium (EU-HCLL), Dual cooled Lead Lithium (US-HCLL), Indian LLCB are some of the concepts being explored worldwide for future fusion reactor [1]. In this scenario, the characterization of Pb-Li alloy becomes important to gainfully...
Dr
Premjit Singh Kongkham
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
This work summaries the experimental studies on joining of tungsten based refractory materials at high temperature using vacuum brazing process. The objective of the joining of these refractory materials is to develop the joining technique for fabricating helium cooled divertor target relevant to DEMO fusion reactor. These so called - divertor fingers - are expected to handle the incident heat...
Dr
Yuki Takemura
(National Institute for Fusion Science)
24/10/2018, 08:30
Poster
The frequency slowing-down mechanism of the locked-mode-like instability without a large
magnetic island is investigated for the first time, based on the LHD experimental analysis.
The slowing-down frequency is caused by two processes. One is the resonant surface moving
to the small E × B rotation frequency region and the other is the slowing-down E × B rotation
frequency around the...
Mrs
Bharathi Magesh
(Institute for plasma research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The detection of a peak corresponding to a hydrogen bearing impurity species (mostly due to water vapour :H20) was reported many times in past while performing the Doppler shift spectroscopy (DSS) diagnostics in several neutral beam injectors based on positive ion sources. However, for the experiments based on negative ion sources, we are reporting the detection of this peak for the first...
Dr
Felipe Bedoya
(MIT-Plasma Science & Fusion Center)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Conditioning of Plasma Facing Components (PFC) is a common practice to improve the plasma performance in both tokamaks and stellarators. The evaporation of thin Li films on the PFC and first wall has given positive results in multiple machines (CDX-U, LTX, TFTR, NSTX, EAST). Reduced recycling and impurity concentration in the plasma are commonly associated with Li. As a consequence, improved...
Dr
Naomichi Ezumi
(University of Tsukuba)
24/10/2018, 08:30
Poster
In Plasma Research Center, University of Tsukuba, divertor simulation experiments have been conducted at the end region of GAMMA 10/PDX. The high temperature end loss plasmas of GAMMA10/PDX are a functional tool for simulating edge and divertor plasmas and contribute to developing a deeper understanding of the physics involved in plasma detachment. Our aim is to study detachment phenomena...
Dr
Jin Myung Park
(Oak Ridge National Laboratory)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Physics based simulations using a new integrated 1.5D core-edge approach for a whole device modeling capability project a compact net electric fusion pilot plant is possible at modest scale based on the advanced tokamak concept, and identify the key parameters for its optimization. These first of a kind reactor simulations provide new insights cf. previous “systems code” projections by...
Dr
Shinsuke OHSHIMA
(Kyoto University)
24/10/2018, 08:30
Poster
The hydrogen/deuterium (H/D) isotope effects on fluctuations and its configuration dependence are studied in a helical device, Heliotron J. The isotope dependence of a toroidally symmetric fluctuation in low frequency range of <~4kHz,, which is considered as a zonal flow, is observed in low-density ECH plasmas in Heliotron J. The long-range toroidal correlation of the low frequency range...
Dr
Christian Day
(Karlsruhe Institute of Technology)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the framework of the EUROfusion Programme the EU is preparing the conceptual design of the fuel cycle for a pulsed fusion DEMO. Over the last years, a completely novel and most innovative fuel cycle architecture has been developed, driven by the need to reduce the tritium inventory to an absolute minimum.
To achieve this goal, batchwise processes used in the fusion fuel cycle so far were...
Dr
Sterling Smith
(General Atomics)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Spin Polarized Fusion (SPF), which increases the DT fusion cross section by 50% and is predicted to yield power gains of 75% in an ITER Q=10 plasma (without SPF), could be demonstrated in the DIII-D tokamak, using recent technological advances. The cross section (probability) for thermal DT fusion is not only temperature dependent, but also depends on the spin orientation of the nuclei,...
Mr
Sayantan Mukherjee
(Kalinga Institute of Industrial Technology,Bhubaneswar,Odhisa(India))
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The thermal performance of plasma facing components in a fusion reactor receiving high heat fluxes could be enhanced significantly by using nanofluid which are suspensions of 0.001-10% nanoparticles of <100nm size. Nanofluids show a promising heat transfer enhancement compared to the base fluid. Water-based nanofluids have the potential to deliver much improved high heat flux cooling while...
Mr
Samiran Shanti Mukherjee
(Institute for Plasma Research)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Cryoadsorption cryopump with large pumping speeds application has been developed at the Institute for Plasma Research (IPR). These pumps are cooled with liquid helium for cryopumping panels below temperature 5K to adsorb hydrogen and helium gases and with gaseous helium for thermal shields at around 80 K during fusion reactor relevant applications. The panels are coated with activated carbon...
Mrs
Deepti dubey
(ITER-India, IPR, Bhat, Gandhinagar, 382428, Gujarat, India)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
An accelerator based 14 MeV neutron source is under development to study the fusion neutronics for Indian fusion programs. The neutrons are generated by impinging 10 mA deuterium beam accelerated up to 340 keV energy over a 140 Curie tritium target. Being a system handling tritium-radio-active material, a recovery system is to be designed to minimize airborne tritium effluent releases to well...
Mr
Timur Tulenbergenov
(Institute of Atomic Energy of National Nuclear Center)
24/10/2018, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The research goals are determining the effect of nitrogen plasma on the tungsten and comparative analysis of the formation of tungsten fuzz on the helium plasma interaction on the initial surface of tungsten and on the surface of tungsten, previously subjected to nitriding. The experiments were carried out on an imitation stand with a plasma-beam installation. The device provides the following...
