Dr
William Morris
(CCFE)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Plasma exhaust is a critical aspect of DEMO-class devices, so there needs to be confidence that it will work. This paper considers the methodology to establish confidence in potential solutions, drawing on approaches inside and outside fusion, including evolving high power computing tools – these approaches could also help find improved solutions, , possibly where all the plasma and materials...
Dr
Keii Gi
(Research Institute of Innovative Technology for the Earth (RITE))
21/10/2016, 08:30
SEE - Safety, Environmental and Economic Aspects of Fusion
Poster
Climate change has become one of the most important issues to be tackled in the world. Deep emission reduction of greenhouse gas must be achieved in this century. In the COP21 of United Nations Framework Convention on Climate Change (UNFCCC) on December 2015 in Paris, a new mechanism of CO2 emission reduction (Paris Agreement) was adopted based on the pledge-and-review approach. Fusion energy...
Mr
Gediminas Stankunas
(Lithuanian Energy Institute)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Activation inventories and decay heat are important nuclear quantities which need to be assessed on a reliable basis for fusion materials for the safe operation of a fusion nuclear power reactor and its final decommissioning. This comparative paper describes the activation and decay heat calculations for WCLL performed in the frame of the EUROfusion WPSAE programme and specifications in...
Prof.
Mikhail Rozenkevich
(D. Mendeleev University of Chemical Technology of Russia)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
One of the most important tasks among initial tasks for realization of the project is to determine different types of the engineering systems which will be required to support of the engineering infrastructure of IGNITOR. One of the most important systems will be tritium fuel cycle and detritiation systems which provides scientific program of the investigation on IGNITOR tokamak. This work...
Dr
GUSTAVO GRANUCCI
(IFP - CNR)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
For the development of a DEMOnstration Fusion Power Plant the design of auxiliary heating systems is a key activity to achieve a controlled burning plasma. The present heating mix considers Electron Cyclotron Resonance Heating (ECRH), Neutral Beam Injection (NBI) and Ion Cyclotron Resonance Heating (ICRH) with a target power to the plasma of about 50 MW for each system. The main tasks assigned...
Prof.
Piergiorgio Sonato
(consorzio RFX)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the framework of the EUROfusion Work Package Heating & Current Drive, a conceptual design of the Neutral Beam Injector (NBI) for DEMO, has been developed by Consorzio RFX in collaboration with other European institutes. High efficiency is a fundamental requirement for DEMO, this has been taken into great consideration for the DEMO NBI, as a fundamental part of the maximization of RAMI...
Dr
Daniel López-Bruna
(CIEMAT)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Magneto-hydrodynamic (MHD) activity is ubiquitous in magnetic confinement plasmas and is related with confinement states. Particularly, confinement quality in TJ-II plasmas is intimately linked to the location and behaviour of magnetic resonances in the plasma column, which often manifest themselves as magnetic islands. Two main physical processes have been identified that relate confinement...
Dr
Jan Stockel
(Institute of Plasma Physics, AS CR)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Small magnetic fusion devices continue to contribute to many areas of fusion research because of their compactness, flexibility, low operation costs and the high skill of their personnel. The concept of interactive co-ordinated joint research using small devices in the scope of IAEA Co-ordinated Research Projects (CRP) was started in 2004 with as overall objective to contribute to streamlining...
Prof.
David Maurer
(Auburn University)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The control of sawtooth oscillations is currently an active area of tokamak research. Large sawtooth oscillations need to be avoided in ITER, since these large sawteeth couple to neoclassical tearing modes and edge localized modes resulting in serious confinement degradation. Small sawtooth oscillations, however, may be beneficial in preventing impurity and helium ash accumulation in the...
Prof.
Xueyu Gong
(University of South China)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The current driven by combined electron cyclotron wave (ECW) and high harmonic fast wave (HHFW) is investigated with the GENRAY and CQL3D package. It is shown that no significant synergetic current is found in a range of cases with combined ECW and FW. This result is consistent with the former study [R.W. Harvey, et al., in Proceedings of IAEA TCM on Fast Wave Current Drive in Reactor Scale...
Weixing Ding
(University of California Los Angeles, California 90095, USA)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Plasma confinement and sustainment of a steady-state tokamak reactor depend on current density profile control to manage MHD instabilities. A number of operational scenarios have been identified for high-performance and high-beta tokamak operation. In these high-temperature plasmas, current transport may occur on time scales much faster than resistive diffusion. Anomalous current transport...
Dr
sergey ananyev
(nrc Kurchatov institute)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
As a part of the nuclear energy Research Center "Kurchatov Institute" development a program of creating a hybrid reactor combining nuclear and thermonuclear technologies was developed and proposed. The basis of a thermonuclear fusion reactor is neutron source (FNS) based on the tokamak [1]. The main difference from the FNS DEMO demonstration fusion reactor is that FNS is not necessary to...
Dr
Cedric Reux
(CEA, IRFM, F-13108 Saint Paul-lez-Durance, France.)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A demonstration power plant is the next step for fusion energy following ITER. The design of such reactors is currently ongoing and still requires solving a number of issues regarding the models used for the different subsystems of the plant. System codes are able to address these questions as they model every major element of the fusion power plant and their interactions. This ensures that...
Dr
Giovanni Grossetti
(DeITKarl)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Power Plant Physics and Technology department (PPPT), being part of the EUROfusion Consortium established in 2014 and composed by European Fusion Laboratories (EFL), aims to develop a conceptual design for the Fusion DEMOnstration Power Plant.
With respect to present experimental machines and ITER, the main goals of DEMO are to produce electricity continuously for a period of 2 to 4...
Dr
Santanu Banerjee
(Institute for Plasma Research)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
SST-1 [1] is a medium sized tokamak with a minor radius of 0.2m, magnetic field of 1.5T and is equipped with heating hydrogen neutral beam capable of delivering 0.5 - 1.7 MW with a variable beam energy of 30-55 keV [2]. The beam parameters provide good candidate for CXRS on SST-1. Using this neutral beam, Charge Exchange Recombination Spectroscopy (CXRS) [3, 4] is proposed for SST-1 Tokamak to...
Dr
Giacomo Aiello
(CEA Saclay)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Helium Cooled Lithium Lead (HCLL) blanket concept is based on the use of Helium as coolant and the eutectic Pb-16Li as neutron multiplier and breeder material. This concept was originally developed in CEA at the beginning of 2000: it is one of the two EU blanket concepts to be tested in ITER in the form of a Test Blanket Module (TBM) and one of the four blanket concepts currently being...
Mr
Thomas Brown
(Princeton Plasma Physics Laboratory)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A Fusion Nuclear Science Facility (FNSF) study based on the Spherical Tokamak (ST) confinement option has progressed through a number of stages of development to understand the requirements to establish a self-consistent conceptual design of an ST-FNSF device. The objective has been to establish sufficient physics and engineering details needed to meet mission objectives centered on achieving...
Dr
rustam khayrutdinov
(NRC Kurchatov Institute)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the present study a method of developing a magnetic control system of the plasma parameters (position, form, current) of the modernized now tokamak T-15 is described. According to the identification of the electromagnetic system and the plasma column of T-15 linear models are built for obtaining control regulators of the two types: 1) proportional-differential regulator to control of plasma...
Mr
Min Xu
(Southwestern Institute of Physics)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Turbulent momentum flux, including the Reynolds stress, convective flux, and the flux driven by nonlinear interactions, was experimentally measured in ELMy H-mode. And it was found that net momentum in the electron diamagnetic direction was injected from the edge into the plasma during ELMs. This is a direct evidence that plasma is able to serve as a heat engine to convert heat into poloidal...
Dr
Flavio Crisanti
(Enea)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A DTT experiment should be capable to: 1) demonstrate a safe and robust power handling solution that can be extrapolated to DEMO; 2) achieve the previous goal without degrading the plasma core and pedestal performances, in a plasma regime as close as possible to a reactor one; 3) demonstrate the possibility to achieve points 1) and 2) by integrating as much as possible all the Physics and the...
Dr
Sergey Lashkul
(Ioffe Institute)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
To explain a relatively good efficiency of LHCD and improved core confinement transition obtained at the small FT-2 tokamak ($R=0.55m$, $a=0.08m$, $B_T \le 3T$, $I_{pl} = 35 kA$, f_0 = 920МHz, Δt_pl = 50ms, Δt_RF = from 30ms to 36ms) [1] a thorough modeling of experimental data has been performed. Effect of LHW on the transition into improved core confinement regime is discussed in the...
Dr
Robert Lunsford
(Princeton Plasma Physics Laboratory)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
We report on ELM triggering and pacing experiments in NSTX-U, including comparisons to pellet ablation models. Multiple sizes and types of solid impurity granules are injected into the low field side of the plasma to determine their ELM triggering and pacing capability. Examining the penetration depths, mass deposition locations, and ELM triggering efficiencies of sub-millimeter lithium,...
Dr
Youwen Sun
(Institute of Plasma Physics, Chinese Academy of Scienses)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
A big progress has been made in the type-I Edge Localized Mode (ELM) control with Resonant Magnetic Perturbation (RMP) on EAST in 2014 and 2015. A flexible in-vessel RMP coil system has been installed in 2014 for active MHD instabilities control to achieve long pulse steady state operation in the EAST tokamak. It can generate a variety range of spectrum covering most important...
Prof.
Minh Quang Tran
(EPFL -CRPP)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
In the frame of the European Fusion Roadmap and under the Power Plant Physics and Technology program, the EUROfusion Consortium is conducting detailed studies on a tokamak DEMOnstration power plant. Scoping studies (e.g. scanning the aspect ratios and the toroidal magnetic field) are being performed. The EU DEMO1-2015 baseline is a 5. 7 T reactor delivering electricity in long pulse (> 2...
Dr
Liang Wang
(Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP))
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Active control of high heat and particle fluxes deposited on the divertor targets is an essential issue for steady-state operations on the experimental advanced superconducting tokamak (EAST) and other future fusion devices, such as ITER. The change of edge magnetic topology is an effective method to exert positive influence on divertor heat and particle fluxes, which has been achieved by...
Dr
Louis ZANI
(CEA-IRFM)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The DEMO reactor is expected to be the first application of fusion for electricity generation in the near future. In the DEMO power plant the management of magnet system is of central importance as being driver on many crucial aspects such as nominal power plant performance (toroidal field scales fusion power), overall investment budget (about 1/3 of the total construction cost), production...
Mr
Min Xu
(Southwestern Institute of Physics)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Sheath potential coefficient α is a very important parameter in Langmuir probe measurement. It is often used to estimate the plasma potential: Vp=Vf+αTe, where Vf and Te are floating potential and electron temperature respectively.In magnetized high temperature fusion plasmas this coefficient is affected by many factors and may lead to large errors in the inferred electric field and fluid...
Dr
Xiaoquan JI
(Southwestern Institute of Physics, Chengdu 610041 China)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
We present the first experimental observation of self-regulation of nonlocal transport events by NTMs generated during transient nonlocal transport events. The nonlocal effect is excited by edge cooling and propagates inward by avalanche events. These cause a local increase of the pressure gradient at the inversion surface, and thus the onset of the NTM in relatively low β plasmas. The...
Dr
Bo Lyu
(Institute of Plasma Physics, Chinese Academy of Sciences)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Rotation driven by radio-frequency waves have been studied on EAST for plasmas heated by LHW, ICRF and ECRH. Understanding of momentum transport characteristics plays an important role in pushing towards RF-heating dominated high-performance plasma operations on EAST. Using newly developed diagnostics, studies on RF-heated plasma rotation and momentum transports have been further carried out....
Dr
Yves Peysson
(CEA)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The radiofrequency (RF) heating and current drive systems play a crucial role in the mission of the Experimental Advanced Superconducting Tokamak (EAST) [1]. RF experiments and modelling were carried out on EAST in 2014-2015, within the framework of the Associated Laboratory ASIPP-IRFM, with the aim to optimise EAST long pulse high performance scenarios. H-mode plasmas have been sustained by...
Dr
Helena Cabal
(CIEMAT)
21/10/2016, 08:30
SEE - Safety, Environmental and Economic Aspects of Fusion
Poster
The first commercial fusion power plants are expected to start operating from 2050. How the global energy system will be as for that time nobody knows, but future can be explored by means of scenarios. In this work, several scenarios have been formulated and represented by the EFDA Times model (ETM), a global optimization energy model developed within the framework of the Socio Economic...
Prof.
MASAYUKI YOKOYAMA
(National Institute for Fusion Science)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The integrated transport analysis suite, TASK3D-a (Analysis), has been developed to be capable for routine whole-discharge analyses of plasmas confined in three-dimensional (3D) magnetic configuration such as the LHD.
The routine dynamic energy balance analysis for NBI-heated plasmas was made possible in the first version released in September 2012, which consisted of four parts: LHD data...
Dr
Annika Ekedahl
(CEA, IRFM)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The passive-active multijunction (PAM), a relevant lower hybrid current drive (LHCD) launcher design, was developed in view of a LHCD system for the second phase of ITER [1]. PAM launchers have so far been successfully tested in L-mode plasmas on FTU [2] and Tore Supra [3]. This paper presents the first ever experiments with a PAM on H-mode plasmas, carried out on HL-2A tokamak [4] as a joint...
Dr
Xiaodong ZHANG
(CnIPPCAS)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
A new divertor concept, the Fishtail divertor (FTD), is proposed and investigated on EAST, which can quickly move the strike point along the radial and poloidal direction like the swing of fishtail by additional alternating magnetic field. The maximum moving distance of the strike point is controlled by the alternating field amplitude. The wetted area of the heat flux is widened, so that the...
Prof.
satoshi konishi
(Kyoto University)
21/10/2016, 08:30
SEE - Safety, Environmental and Economic Aspects of Fusion
Poster
This paper points out one of the critical issue overlooked for fusion to become a viable energy source in the future, quantitatively analyzes the requirements, and suggests a possible solution. Future grids in possible markets and the impact of fusion introduction was analyzed with numerical model, and the limitation and requirements of the generation capacity of fusion plant is shown as the...
Dr
Xinjun Zhang
(Institute of Plasma Physics Chinese Academy of Sciences (ASIPP))
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The paper summarizes the recent experiments performed with Ion Cyclotron Resonance Heating(ICRH) on EAST. Heating and confinement studies using the Hydrogen Minority Heating scheme have been investigated in Ohmic target plasma and in combination with Low Hybrid waves. Energy Confinement follows Scaling Law. The results show a typical L-mode behavior, i.e. a power dependent confinement...
Prof.
Nagato Yanagi
(National Institute for Fusion Science)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
There is considerable progress in conceptual design studies of the helical fusion reactor FFHR-d1. The continuously wound helical coils (major radius 15.6 m) employ the 100-kA-class HTS (high-temperature superconducting) STARS (Stacked Tapes Assembled in Rigid Structure) conductor using a simple-stacking technique of YBCO tapes. A prototype STARS conductor reached 100 kA at 5.3 T and 20 K. A...
Dr
Sergei Lebedev
(Ioffe Physical-Technical Institute, Russian Academy of Sciences)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Bursts of high frequency oscillations have been found in Ohmically heated plasmas in the TUMAN-3M using magnetic probes sited inside vacuum vessel. Typical frequencies of the oscillations are within 0.8-1.8 MHz range. It was found that the frequency of the oscillations followed the dependence of Alfven velocity on toroidal magnetic field and density. This dependence allowed identifying the...
Dr
Marco Ferrari
(Fusion for Energy)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Test Blanket Module (TBM) Program in ITER provides breeder units and related systems with all relevant technologies to test and validate design concepts of tritium breeding blankets for a power-producing reactor, specifically DEMO. Three ports are allocated to the ITER Members (IM’s) participating to the TBM Program and 6 Test Blanket Systems (TBS) are going to be installed and tested...
Ms
Jyoti Agarwal
(Institute for Plasma Research)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Fusion community worldwide is looking forward to an efficient pellet injection system catering to the requirements of fueling high temperature and high density plasma. Various DEMO reactor design world over portray importance underling development of this technology. The important characteristics being looked forward are operational flexibility, high reliability and remote operation with...
Dr
Felix Warmer
(Max Planck Institute for Plasma Physics)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
One of the high-level missions of the European Roadmap for the realisation of fusion energy is to bring the helical-axis advanced stellarator line (HELIAS) to maturity. The near-term focus is the scientific exploitation of the Wendelstein 7-X experiment in order to assess stellarator optimization in view of economic operation of a stellarator fusion power plant.
Meanwhile, the understanding...
Prof.
Yuhong Xu
(Southwestern Institute of Physics)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
“Blob-filaments”, or simply “blobs”, denote radial convection of coherent plasma structures, which transport plasma mass and energy across the open magnetic field line region known as the scrape-off-layer (SOL) and enhance the plasma interaction with the surrounding material boundaries. The generation mechanism for blobs has been investigated for many years. Experiments and...
Mr
A Bader
(Max-Planck-Institute for Plasma Physics)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The paper summarizes the studies carried out on the use of an Ion Cyclotron Range of Frequency System on DEMO in the framework of the PPPT.
An ion cyclotron range of frequency (ICRF) heating system can contribute significantly to various plasma phases during an experimental cycle (‘shot’). It can be used in the plasma start‐up and current ramp-up phase, where election heating is...
Prof.
Xiang Gao
(Institute of Plasma Physics, Chinese Academy of Sciences)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The ITER baseline scenario of the standard H-mode operation (beta-N = 1.8) will be mainly sustained by inductive plasma current drive with the limited pulse duration. Two advanced scenarios of the hybrid scenario (beta-N = 2 ~ 2.5) and steady-state scenario (beta-N > 2.6) are being developed towards long pulse operation in present tokamak devices. A pulse duration of 32 s (about 20R, where R...
Dr
Wei Chen
(CnSWIP)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Kinetic Alfvén-ballooning instabilities (KABIs) are very common in magnetized plasmas both in space and laboratory. In present-day fusion and future burning plasmas, they are easily excited by fast particles and/or pressure gradients. They can not only cause the loss and redistribution of fast particles but also affect plasma confinement and transport. The physics associated with them is an...
Prof.
Chijin Xiao
(University of Saskatchewan)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Plasma flow and its shear in tokamak discharges have many beneficial effects including suppression of turbulence, confinement improvement, control of the resistive wall modes, as well as enhanced tolerance to the error fields which may cause mode locking and even major disruptions. CT injection has also been considered not only as a candidate to directly fuel the core of a tokamak reactor, but...
Mrs
Marta Velarde
(Institute of Nuclear Fusion, UPM-Spain)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Tritium leakages are a major concern regarding nuclear power plants, not only in commercial fission power plants, but also in future fusion power plants. Future fusion reactors, as for example those being studied in the ITER and NIF experiments, will breed tritium from other elements to use it as fuel. Hence, the need for preventing and containing tritium leakages, as it is done with any other...
Dr
Roger Raman
(University of Washington)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Predicting and controlling disruptions is an important and urgent issue for ITER. In support of this activity, NSTX-U will employ three Massive Gas Injection (MGI) valves that are similar to the double flyer plate design being developed for ITER [1]. NSTX-U will be the first device to operate this valve configuration in plasma discharges. NSTX-U experiments will offer new insight to the MGI...
Mr
JongSung Park
(National Fusion Research Institute (NFRI))
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Studies to investigate the feasibility of the divertor system have been proceeding since the pre-conceptual design study on the Korean fusion demonstration reactor (K-DEMO) was initiated in 2012. The divertor is one of the main components and biggest challenges for a tokamak reactor. Its major function is the emission of the heat flux, helium and impurities from the plasma, and also the...
Mr
Chandan Danani
(Institute for Plasma Research, Bhat, Gandhinagar , Gujarat, India-382428)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
SST-2 will be a medium size Indian fusion reactor to be built for realizing the reactor technologies and D-T fuel cycle. It has a low fusion gain (Q = 5) and fusion power output can be from 100 to 300 MW. This work presents nuclear design analyses for SST-2 employing the Indian LLCB (Lead Lithium Ceramic Breeder) blanket for the tritium breeding. The nuclear design analyses address the...
Dr
Carlos Hidalgo
(CIEMAT, Spain)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
In the present paper we have investigated the influence of ECRH on neoclassical and anomalous mechanisms in the TJ-II stellarator. The results reported here were obtained by the use of a unique diagnostic which consists in two Heavy Ion Beam Probe (HIBP) systems located at two different toroidal ports separated by 900. This dual HIBP was used to study the temporal and spatial evolution of...
Prof.
Mikhail Gryaznevich
(Tokamak Energy Ltd)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Recent advances in the development of high temperature superconductors (HTS) and encouraging results on a favourable dependence of confinement on increase in toroidal field (TF) in Spherical Tokamaks (ST) open new prospects for a high field ST as a compact fusion reactor or a powerful neutron source [1]. The combination of the high beta(ratio of the plasma pressure to magnetic pressure),...
Mr
ABHISHEK SARASWAT
(InIPR)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Lead-Lithium Ceramic Breeder Test Blanket Module (LLCB-TBM) is the Indian TBM representing the DEMO breeding blanket, to be installed in ITER radial port no-2. The prime testing objective of LLCB TBM in ITER is to generate experimental data on the performance of tritium breeding blankets (such as tritium breeding and its extraction, nuclear heat extraction, neutron shielding) in an...
Mr
Nobuyuki Asakura
(Japan Atomic Energy Agency)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Handling of a large exhausted power to the SOL and divertor is the most important issue for DEMO reactor design. The plasma concept (Ip = 14 MA, R = 8.5 m, a = 2.5 m) with the reduced fusion power of 1.5 GW and central solenoid coils sufficient for inductive start was proposed. Plasma simulation of the power exhaust and engineering design of tungsten (W) plasma-facing-component and...
Dr
Kieran Joseph McCarthy
(Laboratorio Nacional de Fusion, Ciemat)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Core plasma fuelling is a critical issue on the pathway to developing steady-state scenarios in 3-dimensional magnetically confined plasma devices. Indeed, neoclassical theory predicts that on-axis electron cyclotron resonance heating (ECRH) requires a particle source situated at the same radial position as ECRH with an analogous deposition profile shape in order to mitigate potential core...
Dr
Teresa Estrada
(CIEMAT)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The effect of magnetic islands on plasma flow and turbulence is experimentally investigated in ohmically induced magnetic configuration scans at TJ-II. This operational mode allows sweeping the radial position of a low order rational surface in a controlled way, what reveals effects that are difficult to notice in scans performed on a shot to shot basis. The main diagnostic used in the present...
Dr
Ronald Wenninger
(Max-Planck-Institut für Plasmaphysik)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The development of a conceptual design for a demonstration fusion power plant (DEMO) is a key priority of the recent European fusion program [1]. The DEMO design/R&D is expected to benefit largely from the experience gained with ITER construction and operation, but there are still outstanding gaps requiring a vigorous physics and technology R&D programme. The constraints coming from specific...
Dr
Guoqiang Li
(Institute of Plasma Physica, CAS)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The Chinese Fusion Engineering Test Reactor (CFETR) is under design. The machine aims to fill the gaps between ITER and DEMO. Recently, the physical design focuses on the so-called baseline scenario. It is a 10 MA steady state scenario to produce ~200 MW fusion power. With the integrated modelling of the equilibrium calculation, pedestal structures prediction, 1.5D core transport simulation,...
Dr
George Neilson
(Princeton Plasma Physics Laboratory)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A conceptual design study for a steady-state fusion demonstration reactor, K DEMO, has been undertaken by the National Fusion Research Institute (NFRI) in the Republic of Korea. Analyses of the plasma heating and current drive configuration and of the tokamak configuration have continued in support of the study. It is assumed that a combination from among at least the standard heating and...
Ms
Jyoti Agarwal
(Institute for Plasma Research)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The exhaust from a fusion grade machine comprises mainly isotopes of hydrogen gas and helium as the main content. The challenge lies in pumping voluminous amount of exhaust gases of the order of 200-400 Pa.m3/s. At present, pumping such a large throughput of gas in a perpetual way is a topic of primary focus in the field of vacuum science. Important requirement is of establishing technology at...
Xue Zhou Jin
(DeITKarl)
21/10/2016, 08:30
SEE - Safety, Environmental and Economic Aspects of Fusion
Poster
Following the European roadmap to the realisation of fusion energy, a demonstration fusion power plant (DEMO) is currently in pre-conceptual design phase till 2020. In this context an external stakeholder group formulated a nuclear licensed manufacturing and construction (M/C) as the top level requirement for a DEMO, translating essentially to the confinement of radioactive and hazardous...
Dr
B J Ding
(Institute of Plasma Physics, Chinese Academy of Science)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
To explore lower hybrid current drive at reactor relevant, high density is an important issue. Collisional absorption (CA), parametric instabilities (PI) and scattering from density fluctuations (SDF) are considered as possible candidates for the current drive (CD) efficiency decreasing faster than theory prediction. A multi-machine assessment, including experiments and modeling in EAST, C-Mod...
David Schissel
(General Atomics)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Scientists at General Atomics (GA) have conducted in the United States remote experimental operation of the Experimental Advanced Superconducting Tokamak (EAST) in China during their third shift. These experiments were led by scientists in a dedicated remote control room that utilized a novel computer science hardware and software infrastructure to allow data movement, visualization, and...
Dr
Junichi Miyazawa
(National Institute for Fusion Science)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A new liquid metal divertor concept named the REVOLVER-D (Reactor-oriented Effectively VOLumetric VERtical Divertor) has been proposed for the helical fusion reactor FFHR-d1. The REVOLVER-D consists of molten tin shower jets stabilized by chains set inside each jets. These are installed in 10 inner ports of FFHR-d1 to intersect the ergodic layer surrounding the last-closed-flux-surface. The...
Dr
Zhongbing Shi
(Southwestern Institute of Physics)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
In the next generation of large fusion device ITER, it has been accepted that the divertor could not endure the heat exhaust due to the edge localized modes (ELM), without any action to mitigate. The physical mechanism and controlling methods of ELM have become the important tasks in physics of boundary plasmas. The supersonic molecular beam injection (SMBI), one of numerous approaches to...
Prof.
Jiaqi Dong
(Southwestern Institute of Physics)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Detailed analyses of the dynamic evolutions of the pedestal, including density, temperature, pressure and their gradients were performed in recent H-mode experiments on HL-2A tokamak. Dramatic increase of density gradient and decrease of electron temperature gradient were observed in the pedestal just prior to each burst in a series of ELM eruptions. An inward particle flux inducing...
Mr
Alexander Shevelev
(RuIoffe)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Analysis of the super-thermal and runaway electrons behavior in ohmic and low-hybrid current drive FT-2 tokamak ($R=0.55m, a=0.08m, B_T≤3T, I_pl =32kA, \langle n\rangle = 1.9 \times 10^{19}m^{-3}, f_0=920МHz$) plasmas has been carried out using information obtained from measurements of hard X-ray spectra and non-thermal microwave synchrotron radiation intensity in the frequency range (53 ÷ 78)...
Dr
Youji Someya
(Japan Atomic Energy Agency)
21/10/2016, 08:30
SEE - Safety, Environmental and Economic Aspects of Fusion
Poster
This paper presents safety and waste management studies for a fusion DEMO reactor. It was found that an impact of a large-scale ex-vessel loss-of-coolant accident (LOCA), i.e., a guillotine rupture of a main pipe of the primary cooling system with pressurized water reactor (PWR) condition (320ºC, 16 MPa), can be mitigated by using a vault for the Tokamak Cooling Water System (TCWS) with a...
Prof.
Dennis Whyte
(MIT Plasma Science Fusion Center)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The recent industrial maturation of high-temperature, high-field superconductors opens up a faster and cheaper development path for fusion energy by enabling reactor-level performance at smaller scale. The current fusion energy development path, based on large volume moderate magnetic B field devices is proving to be slow and expensive. A development effort is underway on new superconductor...
Dr
Ana Prades
(CIEMAT)
21/10/2016, 08:30
SEE - Safety, Environmental and Economic Aspects of Fusion
Poster
Collecting scientific evidence on the human, social and ethical dimensions in energy systems is a fundamental tool for understanding (and intervening in) the acceptance of energy technologies, the siting of energy generation facilities, and the promotion of measures for risk mitigation and safety. Furthermore, this key role of social research in energy fully aligns with proposals for more open...
Dr
FARAH DEEBA
(National Tokamak Fusion Program, Pakistan)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
Optical emission spectroscopy is applied as a diagnostic tool to investigate the plasma in GLAST-III (glass spherical tokamak) at different scenarios. It is a small limiter device having aspect ratio (R/a = 2) with major radius R = 20 cm and minor radius a = 10 cm. Spectral analysis is performed to study the plasma induced optical emission and the electron temperature for different values of...
Dr
Vladimir Minaev
(Ioffe Institute, St. Petersburg, Russian Federation)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The Globus-M spherical tokamak has demonstrated practically all of the project objectives during the 15-year period of operation. The main factor limiting further enhancement of plasma parameters is a relatively low toroidal magnetic field. The increasing of the magnetic field up to 1.0 T together with the plasma current up to 0.5 MA will result in the significant extension of the operating...
Dr
Petr Khvostenko
(NRC"Kurchatov Institute")
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Presently, the Tokamak T-15MD is being built. The magnet system of the Tokamak T-15MD will obtain and confine the hot plasma in the divertor configuration. Plasma parameters are a major radius of 1.48 m, a minor radius of 0.67 m, an elongation of 1.7-1.9 and a triangularity of 0.3-0.4. Tokamak T-15MD will equipped with the auxiliary plasma heating and current drive (Paux =15 - 20 MW) systems....
Prof.
Artur Malaquias
(Instituto Superior Tecnico, Universidade de Lisboa)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
It has been experimentally established in ISTTOK that edge electrode biasing under appropriated conditions improves confinement by reducing radial transport. In order to improve the repeatability and reproducibility of AC operation edge electrode biasing was used to assist the transition of plasma current applied at different time lapses of the AC discharge. This paper presents the results of...
Prof.
Zhengying Cui
(Southwestern Institute of Physics)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
In next-generation fusion devices the reduction of impurity concentration in core plasmas is of great importance not only for the decrease in the line radiation loss but also for mitigation of the fuel dilution and the bremsstrahlung radiation to achieve high-performance plasmas in the high density regime. In experiments, the electron cyclotron resonance heating (ECRH) has been widely applied...
Dr
Longwen Yan
(CnSWIP)
21/10/2016, 08:30
EXC - Magnetic Confinement Experiments: Confinement
Poster
The synchronization of geodesic acoustic modes (GAMs) and magnetic fluctuations is identified in the edge plasmas of the HL-2A tokamak for the first time. The frequency entrainment and phase lock are elucidated. Meso-scale electrostatic fluctuations (MSEFs) with components of the dominant GAMs and the m/n = 6/2 potential fluctuations are found to have the same frequency as magnetic...
Dr
Subrata Pradhan
(Institute for Plasma Research)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The superconducting magnets system (SCMS) of the fusion devices e.g. tokamak / stellarator consists of complex superconducting magnetics. In order to supply such high currents from the power supplies to the SCMS, many numbers of current leads (CLs) are required in the range of 4.5 K – 300 K. As the studies revealed that based on the duty cycle of operation of fusion device, almost 25% - 30% of...
Mr
Eric Villedieu
(CEA-IRFM)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Fusion Tokamaks are complex machines which require special conditions for their operation, in particular, high vacuum inside the vessel and high temperature of the vessel walls. During plasma phases, the first wall components are highly stressed and the control of their surface is necessary in case of doubt about their condition. To be able to make safely such an inspection in a short period...
Dr
Jean-Claude Vallet
(CEA)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
The CEA contributions to the Broader Approach projects, IFERC, IFMIF and JT-60SA which included the deliveries of components and services are now approaching completion. For IFERC, the supercomputer Helios, provided by CEA, will perform until the end 2016 its last runs after 5 years of operation close to its nominal capabilities. For IFMIF, the CEA contributions include the deliveries and the...
Mr
qiyong zhang
(Institute of plasma physics Chinese Academy of sciences)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
Since the first commissioning in February 2006, EAST cryogenic system has been in operation for eleven plasma experiment campaigns with high reliability. However, ten years have passed from the beginning of the system operation. With requirements of EAST physical experiment, new users of cryogenic system have been added such as cryopump, pellet inject and NBI. Some upgrades have been...
Mr
Chandan Danani
(Institute for plasma research)
21/10/2016, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Poster
A key step towards a DEMO reactor and beyond is the development of key facilities addressing various engineering and physics issues. In the Indian plan, SST 2 is under consideration as a low Fusion gain (Q =5) Reactor for realizing and qualifying technologies for D-T fusion cycle and for the Indian DEMO programme [1][2]. The 0 D physics design of SST 2 is done using the 0 D systems code...
