-
Mr Xin Chen05/06/2017, 13:40Operations and maintenancePoster
According to the needs of the development of China nuclear fusion research, HL-2M is being built in Southwestern Institute of Physics (SWIP) as a transformation and upgrade device of HL-2A ,which is a plasma physics and controlled nuclear fusion tokamak experimental platform. The liquid helium cryogenic system (LHCS) with a 500W@4.5K power is under construction to provide a cryogenic and...
Go to contribution page -
Mr Zichu Huang05/06/2017, 13:40Diagnostics and instrumentationPoster
More and more Tokamak devices have been designed and constructed to challenge the controlled fusion problem, such as ITER, J-TEXT, EAST and HL-2M. The coil systems of the Tokamak devices are usually composed of Poloidal Field (PF) coils, Toroidal Field (TF) coils and Central Solenoid (CS) coils. Among them, the PF coils play a role for adjustment of the confining magnetic field to control the...
Go to contribution page -
Alexander Nagy (PPPL)05/06/2017, 13:40Plasma-material interactions, plasma edge physicsPoster
Injection of solid non-fuel pellets has been actively used as a tool for pacing and mitigation of edge localized modes (ELMs). In DIII-D, effective ELM pacing has been demonstrated by high frequency injection of Li and C sub-millimeter spheres, using the Impurity Granule Injector (IGI) [1], which injects granules into the plasma at speeds up to 150 m/s, through impact with a rotating impeller....
Go to contribution page -
Mr Yanwei Liu (Institute of plasma physics, Chinese Academy of Sciences)05/06/2017, 13:40Materials and fabricationPoster
Graphite is used as plasma facing material in EAST lower divertor consisting of hundreds of graphite tiles which are connected to heat sink using screw bolt currently. A soft graphite sheet is inserted between graphite tile and heat sink to improve the ability of thermal conductivity. To evaluate the quality of the thermal contact between graphite tile and heat sink , efficient non-destructive...
Go to contribution page -
Dr Mirela Cengher (General Atomics)05/06/2017, 13:40Plasma heating and current drivePoster
The DIII-D electron cyclotron heating system (ECH) has six gyrotrons installed at this time and is operated for injection into the plasma of rf power up to 3.6 MW at 110GHz frequency. The rf power injected at the tokamak is measured on a shot to shot basis with a calibration based on the heat deposition in the gyrotron water cooling circuits.
Go to contribution page
A technique for calibrated ECH power measurement... -
Mr Nikola Jaksic (Max Planck Institute for Plasma Physics, EURATOM Association)05/06/2017, 13:40Plasma facing componentsPoster
The solid tungsten divertor tiles at ASDEX Upgrade experimental device have been gradually installed as substitution for W coated graphite tiles in 2012.
Go to contribution page
ASDEX Upgrade is equipped with an adiabatically loaded divertor as a compromise between available heating power, plasma discharge length and heat removal capability of divertor tiles. Accordingly, the design of the new solid tungsten plates... -
Mr Yang Zhigang (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Power supply systemsPoster
4.6GHz/6MW Lower Hybrid Current Drive (LHCD) is one of plasma current heating methods for Experimental Advanced Superconducting Tokamak (EAST). High Voltage Power Supply (HVPS) is the power supply subsystem of 4.6GHz/6MW LHCD system, which was designed, built and accepted successfully by Chinese National Development and Reform Commission in 2015. Then the new system has been in use for the...
Go to contribution page -
Mr Xiaosong Fan05/06/2017, 13:40Materials and fabricationPoster
China Fusion Engineering Test Reactor (CFETR) vacuum vessel (VV) is a forming and welding product, which is composed of formed shells and ribs, and welded to a toroidal double shell structure device. However, there are manufacturing errors in the manufacturing process, which will lead to accumulative deviation of the VV dimensions and affect the VV contour and the welds quality. To reduce and...
Go to contribution page -
Jie Xu05/06/2017, 13:40Plasma operation and controlPoster
In order to improve the capability of Tokamak measurement and control system, centralized measurement and control system with compatibility and continuous upgrade ability is needed to build. EPICS has advantages of safety, easy expansion etc. in this paper, HL-2A host centralized control system based on EPICS is developed and designed. Communication between SoftIOC and PLC was realized using...
Go to contribution page -
Cyril BRUN (CEA)05/06/2017, 13:40Operations and maintenancePoster
Since 2013 Tore Supra has turned to WEST (Tungsten (W) Environment in Steady state Tokamak) Platform targeted at supporting the ITER divertor detailed design, manufacturing and future operation. The major changes included the modification of the magnetic configuration (from limiter to divertor), the replacement of carbon plasma facing components by new tungsten plasma facing components (PFCs),...
Go to contribution page -
Dr Wei Zheng05/06/2017, 13:40Project management, systems engineeringPoster
With the rapid growing of experiment data, widely using of distributed database or file system will be the trend in future fusion storage. For such storage systems, a cluster is required, but its setting up and service’s deploying are challenging. Besides, plenty of configurations should be set carefully, including environment variable and software runtime, which is a complicated task. Apart...
Go to contribution page -
Mr Christian Gómez-Samaniego (CICATA Queretaro-IPN)05/06/2017, 13:40Plasma-material interactions, plasma edge physicsPoster
Previous research has demonstrated that linear plasma accelerators can achieve the energy, temperature and densities necessary to reproduce the conditions of plasma impact in a divertor plate [1]. Some initial experiments have been performed with plasma foci at University of Mexico [2]. At the Instituto Politecnico Nacional a new device, a flexible Plasma Gun that can be operated in snowplow...
Go to contribution page -
Dr Dehong Chen (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)05/06/2017, 13:40Next step devices, DEMO, power plantsPoster
Gas Dynamic Trap (GDT) is very attractive as a kind of fusion neutron source for testing fusion material and component as well as driving transmutation reactor due to its linear and compact structure, easiness of construction and maintenance, relatively low cost and tritium consumption. These years, the conceptual designs of GDT-based neuron source for above two purposes, named FDS-GDT, have...
Go to contribution page -
Mr Shusheng Wang05/06/2017, 13:40Power supply systemsPoster
The conceptual design of quench protection circuit for CFETR (China Fusion Engineering Testing Reactor) rated for current up to 70 kA and voltage of 15 kV is presented. The proposed scheme is based on a mechanical switch paralleled to the controlled static breaker. Static breaker is composed of a IGBTs unit and four diode units in a rectifier bridge allows it to be used in both current...
Go to contribution page -
Mr Xiaogang Liu (Institute of Plasma Physics Chinese Academy of Sciences)05/06/2017, 13:40Next step devices, DEMO, power plantsPoster
China is planning to construct the China Fusion Engineering Test Reactor (CFETR), in order to bridge the gap between ITER and the Prototype Fusion Power Plant. The cryogenic system of CFETR is indispensable to provide cooling for the superconducting magnet system and cold structures at 4.2 K, the cryopumps at 3.7 K, the HTS current lead at 50 K, and the thermal shields at 80 K. In this paper,...
Go to contribution page -
Dr Chen Chen05/06/2017, 13:40Fueling, exhaust, and vacuum systemsPoster
A torus exhaust pumping system comprising 6 identical cryosorption pumps for China Fusion Engineering Test Reactor (CFETR) is designed to provide specified pressure levels and throughputs for various plasma operation modes. A conceptual structural design is performed and recommendations are presented in accordance with the design requirements. Based on the analysis of conductance, the...
Go to contribution page -
Stefan Marsen (Max-Planck-Institut für Plasmaphysik)05/06/2017, 13:40Plasma heating and current drivePoster
W7-X is a steady state capable optimized stellarator. The main heating system is electron cyclotron resonance heating (ECRH) operating at 140GHz providing up to 9MW microwave power.
Go to contribution page
A set of diagnostics has been developed to protect the machine from non absorbed ECRH power which can easily damage in vessel components.
The power is launched into the machine by front steerable quasi-optical... -
Mr Wenjin Chen05/06/2017, 13:40Diagnostics and instrumentationPoster
The safety factor and current density profiles play a very important role in understanding magnetohydrodynamics and micro-instability. Motional Stark effect (MSE) is one of the most powerful tools to measure the current density. A 4-channel MSE polarimeter based on dual photo-elastic modulators (PEMs) has been developed in the HL-2A tokamak. For each channel, 6 1-millimeter silicon fibers are...
Go to contribution page -
Dr Liu Changle (Institute of Plasma Physics, CAS)05/06/2017, 13:40Next step devices, DEMO, power plantsPoster
The main function of the CFETR shield blanket (SB) system is to provide the neutron shielding capability for the in-vessel components and the external environment. The SB concept design has been carried out during the 2009-2011 campaign. The current design on the SB system is concentrated on the neutronics analysis, the SB modules design, and the mechanics analysis using finite element method...
Go to contribution page -
Dr Xiuqing Zhang (Institute of Plasma Physics Chinese Academy of Sciences)05/06/2017, 13:40Power supply systemsPoster
The external bypass, as an important components of the international thermonuclear experimental reactor (ITER) poloidal field converter unit (PFCU), will provide a freewheeling loop for the load current to protect the magnets and PF converter modules from being damaged by over-current and over-voltage under fault conditions. The triggering bypass protection test is used to verify that the...
Go to contribution page -
Dr Yong Ren05/06/2017, 13:40MagnetsPoster
Yong Ren*, Xiaogang Liu, Zhaoliang Wang, Junjun Li, Shijun Du, Guoqiang Li, Xiang Gao
Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences, PO Box 1126, Hefei, Anhui, 230031, People's Republic of China
*E-mail: renyong@mail.ustc.edu.cn; renyong@ipp.ac.cn.Abstract—The China Fusion Engineering Test Reactor (CFETR), which has the potential to produce a...
Go to contribution page -
Mr Zhongma Wang (Institute of Plasma Physics Chinese Academy of Sciences)05/06/2017, 13:40Safety and environmentPoster
High power aluminum water-cooling DC busbar is used to connect the converter and the reactor for the ITER PF converter. The water temperature difference between import and export is less than 20℃, and the temperature rise of the busbar does not exceed 70℃ according to the ITER standards. Three DC busbar connection types is designed to resolve soft connection overheat under the rated current....
Go to contribution page -
Dr ZHU Liang (ASIPP)05/06/2017, 13:40Plasma heating and current drivePoster
The paper describes the design process and experimental validation of a local oscillator for the lower hybrid current system(LHCD) on EAST. The local oscillator is designed to provide original RF energy for the whole LHCD system, which plays an important role. The local oscillator must be of high spectral purity and stability. Only phase noise is better than -90dBc/10KHz can satisfy the...
Go to contribution page -
Weiguo Que (Princeton Plasma Physics Laboratory)05/06/2017, 13:40MagnetsPoster
A ground plane is a conductive, grounded, electrostatic shield surrounding high voltage insulated conductors. The purpose is to contain the electric field developed by the high voltage conductors within the insulation and to provide a return path for capacitive currents during transients.
Go to contribution page
A resistive paint was applied to the outer surfaces of the NSTX-U OH coil to form an outer ground plane.... -
Dr Deyong Song (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Power supply systemsPoster
In Experimental Advanced Superconducting Tokamak (EAST), Resonant Magnetic Perturbation (RMP) coils, which are powered by RMP coil Power Supply (PS), are set to research Edge Localized Mode (ELM), Resistive Wall Mode (RWM) and Error Field Correction (EFC). The RMP coils are grouped in 8 sets with 2 coils in series as 1 set. And the 8 sets of coils are respectively powered by 8 sets of PSs.
Go to contribution page
... -
Dr Zhiyuan Weng (Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP))05/06/2017, 13:40Power supply systemsPoster
Abstract—Magnetic compression (MC) technology was suggested for tokamak to study compressed plasma in [Li, G., Scientific reports, 2015, 5] and a power module is designed here for developing its server power supplier. The minor-radius compression is one of the most effective method to improve the performance parameters of existing tokamaks, enabling the plasmas operated at high density, high...
Go to contribution page -
Dr Victor Udintsev (ITER Organization)05/06/2017, 13:40Diagnostics and instrumentationPoster
Most of ITER’s diagnostics will be provided with viewing lines (optical, microwave, spectroscopic) for the monitoring of key characteristics of the plasma or for the achievement of physical measurements inside the vacuum vessel. The nature of the physical signal transmitted through the viewing lines requires the implementation of window assemblies incorporating non-metallic window. Placed at...
Go to contribution page -
Mrs Bo Shi (Institute of Applied Physics of AOA)05/06/2017, 13:40Divertors and high heat flux componentsPoster
H-mode with ELMs (Edge Localized modes) plasma regime is considered to be a preferable scenario in the future fusion devices as ITER. Heat loads on divertor during ELMs especially the type I ELMs is an important issue [1-2]. An infrared (IR)/visible endoscope system was built on the Experimental Advanced Superconducting Tokamak (EAST) in 2014. Based on the IR data in the experiment of 2014,...
Go to contribution page -
Dr Fan Feng05/06/2017, 13:40Materials and fabricationPoster
Tungsten materials have been attracting growing interest as a promising candidate for plasma facing materials (PFMs) based on its high melting point, high temperature strength, and good thermal conductivity as well as its low erosion in fusion radiation environment and low tritium retention. But the inherent disadvantages of tungsten materials, including poor low temperature machinability, low...
Go to contribution page -
Mrs Alina Elena Niculescu (ICSI Rm. Valcea, Romania)05/06/2017, 13:40MagnetsPoster
The International Thermonuclear Experimental Reactor(ITER) device should demonstrate the scientific and technological possibility of commercial fusion energy production in large scale in order to solve the worldwide energy problem in the future. The superconducting magnet system is the key part of the ITER device to supply high magnetic fields for confining the deuterium–tritium plasma. The...
Go to contribution page -
Mr russell feder (pppl)05/06/2017, 13:40Diagnostics and instrumentationPoster
ITER diagnostic port plugs perform many functions including nuclear shielding, structural support of diagnostic system, while allowing for diagnostic access to the plasma. With design advancing, the in-port diagnostic components are integrated into the port plug structure, and the diagnostic shield modules (DSM) are customized to accommodate various in-port diagnostic components. This paper...
Go to contribution page -
Mr Anatoly Panin (Forschungszentrum Juelich GmbH)05/06/2017, 13:40Neutronics and multiphysics simulationPoster
Forschungszentrum Jülich and partners have been developing the ITER upper port plug diagnostic system (cCXRS) that is to transmit the visible light from the plasma to the end diagnostic via optical mirrors.
Go to contribution page
Each port plug (PP) and its on-board components should withstand severe loads due to the plasma transients when the eddy currents and electromagnetic (EM) forces occur in the PP massive... -
Mr hui bao (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Blankets and tritium breedingPoster
Square channel is widely used in the conceptual design of water cooled blanket of fusion reactor for cooling and providing appropriate inner temperature field for tritium breeding. Blanket is one of the most important safety components and thermal-hydraulic characteristics of blanket directly determine the heat transfer efficiency and safe operation of fusion reactor. Under accident...
Go to contribution page -
G. Douglas Loesser (Princeton Plasma Physics Laboratory)05/06/2017, 13:40Divertors and high heat flux componentsPoster
A divertor “scraper” has been designed to protect weakly-cooled regions of the Wendelstein 7 X (W7-X) divertor targets from overheating under certain steady-state conditions [1]. The scraper is a limiter-like component with a plasma-facing profile geometry that was numerically designed to shadow those vulnerable target regions under such conditions. The “TDU” scraper is an inertially cooled...
Go to contribution page -
Mr Chi Wang (Southwestern Institute of Physics)05/06/2017, 13:40Power supply systemsPoster
An energy-stored impulse motor-generator (MG) is used in power supply system of HL-2A tokamak to produce short high-voltage or high-current surges of desired parameters that are usually used for magnetic field coils and auxiliary heating equipment loads. The operation changing of these loads will cause disturbances in generator’s terminal voltage and the remark drop in MG’s rotating speed....
Go to contribution page -
Xiang Zhu05/06/2017, 13:40Diagnostics and instrumentationPoster
A novel method has been developed to improve the accuracy of plasma current density profile by combining the polarimeter/interferometer (POINT) measurements with the external magnetic measurements on the EAST tokamak. The POINT system, measuring the accurate line-integrated electron density and Faraday rotation angle, provides the magnetic field information inside the plasma. By adding these...
Go to contribution page -
Dr Yosuke HIRATA (National Institute for Quantum and Radiological Science Technology, IFMIF Accelerator Group)05/06/2017, 13:40Diagnostics and instrumentationPoster
ACCT/DCCTs are used as a non-interceptive means of beam current measurement in the IFMIF/EVEDA accelerator. Current measurement using ACCTs for long pulses with 100 ms or longer suffers such problems as drooping due to the fact that this measurement is based on the current induction through transformers. The electrical circuits connected to ACCT have been improved in order to reduce the...
Go to contribution page -
Nikolai Norausky (General Atomics)05/06/2017, 13:40MagnetsPoster
General Atomics is currently fabricating seven (six plus one spare) modules for the ITER Central Solenoid in its Poway, CA facility. One of the critical steps in developing the fabrication process for the modules was to develop the insulation system providing the electrical isolation between turns and to grounded components. The insulation system for a module was required to withstand a...
Go to contribution page -
Dr Mario Pillon (ENEA)05/06/2017, 13:40Neutronics and multiphysics simulationPoster
A neutronics integral benchmark experiment on a pure Copper block (dimensions 60x60x60 cm3), aimed at testing and validating recent nuclear data libraries has been performed at GELINA. GELINA is a powerful photo-neutron source using 75 A, 110 MeV electron current impinging on a depleted 238U rotating target, producing a white spectrum with neutron energies ranging from epithermal region up to...
Go to contribution page -
Dr Wei Wen (ASIPP)05/06/2017, 13:40MagnetsPoster
The Poloidal Field (PF) coils are one of the main sub-systems of the ITER magnets. The PF6 coil is being manufactured by the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) as per the Poloidal Field coils cooperation agreement signed between ASIPP and Fusion for Energy (F4E). The ITER PF6 winding pack is composed by stacking of 9 double pancakes. Dummy double pancake...
Go to contribution page -
Mr Rabel Rizkallah (University of Illinois)05/06/2017, 13:40StellaratorsPoster
The Hybrid Illinois Device for Research and Applications (HIDRA) is a toroidal fusion device at the University of Illinois. HIDRA is the former WEGA stellarator that was operated in Greifswald at the Max Planck Institut für Plasmaphysik. The machine is a five period, l = 2, m = 5 stellarator, with major radius $R_0$ = 0.72 m and minor radius r = 0.19 m. Initial heating is achieved with 2.45...
Go to contribution page -
Didier Chauvin (CEA)05/06/2017, 13:40Diagnostics and instrumentationPoster
The Wendelstein 7-X fusion experiment at Max-Planck-Institut für Plasma Physik (IPP) in Greifswald produced its first hydrogen plasma on 3rd February 2016. This marks the start of scientific operation. Wendelstein 7-X is to investigate this configuration’s suitability for use in a power plant. In order to allow for an early integral test of the main systems needed for plasma operation (magnet...
Go to contribution page -
Dr Wei Lu (Institute of Applied Physics, Army Officer Academy)05/06/2017, 13:40Blankets and tritium breedingPoster
As a notable multifunctional material in breeding blankets, Li2Be2O3 could play a role on both tritium breeder (lithium) and neutron multiplier (beryllium), which is being considered for use in increasing the tritium breeding ratio. However, synthesis of Li2Be2O3 ceramic powder still needs to be further studied, and the preparation of Li2Be2O3 pebble-type breeder has not been reported in...
Go to contribution page -
Dr Dang Cai (Princeton Plasma Physics Lab)05/06/2017, 13:40Plasma-material interactions, plasma edge physicsPoster
The National Spherical Torus eXperiment (NSTX) has recently undergone a major upgrade to NSTX-U at Princeton Plasma Physics Laboratory (PPPL). To improve plasma performance for NSTX-U, control of the influx of impurity gases and fuel recycling from plasma facing components (PFCs) are critical. On the NSTX fusion device, two lithium oven evaporators (LITERs) were mounted on the upper dome of...
Go to contribution page -
Dr Luis Delgado-Aparicio (Princeton Plasma Physics Laboratory)05/06/2017, 13:40Diagnostics and instrumentationPoster
In the ITER (International Thermonuclear Experimental Reactor) program, core imaging X-ray spectrometer (CIXS) and electron cyclotron emission (ECE) are two diagnostic systems in the US ITER project, where X-ray Dectric PILATUS single-photon-counting pixel detectors for X-ray energy and piezo actuators are required to operate under the conditions of high magnetic fields and the accompanying...
Go to contribution page -
Prof. Tianxi Zhang (Alabama A & M University)05/06/2017, 13:40Plasma heating and current drivePoster
Ten-thousand-fold enhancements of $^3$He abundance in impulsive solar energetic particle (SEP) events indicate that $^3$He ions, before accelerated to high energies (~ 1 MeV/nucleon) in solar flares, should have been preferentially heated significantly ($T_{^3He}/T_{^4He} ~ 10 - 100$). The best mechanism developed so far for preferential heating of $^3$He is the first or second harmonic...
Go to contribution page -
Prof. Martin Nieto-Perez (CICATA Queretaro - IPN)05/06/2017, 13:40Neutronics and multiphysics simulationPoster
Two of the main cited flaws of nuclear fission power to label it as a non-sustainable energy source are linked to the nuclear fuel cycle: one is the fuel availability, and the other is the radioactive spent fuel legacy. The incorporation of fast neutron systems to the fuel cycle can help reduce this two problems, by breeding additional fissile material (thus extending the nuclear resource's...
Go to contribution page -
Dr Jinhong Yang (New Star Research Institute of Applied Technology)05/06/2017, 13:40Plasma operation and controlPoster
A simulation of J-TEXT Ohmic disruptive discharge has been achieved by using of the Tokamak Simulation Code (TSC) model. The anomalous transport of disruption was adjusted according to heat transport across large magnetic island. The simulation result of the plasma current, electron temperature, loop voltage and the disruption are compared with experimental disruptive discharge data. According...
Go to contribution page -
Dr Xiaofeng Han05/06/2017, 13:40Diagnostics and instrumentationPoster
The high temporal and spatial resolution of laser Thomson scattering (TS) diagnostics is an important research subject of fusion plasma diagnostics. Currently, the temporal resolution of TS based on single laser in EAST is limited to 20 ms, which is too low to resolve the evolution of pedestal structures directly. A critical part of this diagnostic is the high-frequency laser source. A...
Go to contribution page -
Peter Spaeh (KIT)05/06/2017, 13:40Neutronics and multiphysics simulationPoster
In four of the upper ports of ITER, Electron Cyclotron launchers will be installed for heating and plasma stabilization. The launchers are designed as stainless steel casks (so-called port plugs), accommodating microwave mirrors and waveguides with the capability to inject up to 24 MW total microwave power into the plasma.
The inner volume of the port plugs represents a relatively open...
Go to contribution page -
Dr Jie Zhang05/06/2017, 13:40Neutronics and multiphysics simulationPoster
The conceptual design of Chinese Fusion Engineering Reactor (CFETR), which will be operated in two phases has been proposed to fill the gap between ITER and DEMO plant [1]. In order to maintain the performance of Vacuum vessel (VV) and external machine components especially the superconductors, a reasonable shielding blanket is needed between tritium breeding blanket (BB) and those...
Go to contribution page -
Dr Reinhard Vilbrandt (Max-Planck-Institute for Plasma Physics, D-17491 Greifswald, Germany)05/06/2017, 13:40Safety and environmentPoster
After the successful first operation campaign of Wendelstein 7-X in 2016 the experiment is being upgraded for the next stage called OP 1.2.
Go to contribution page
Due to some new or extended components like heating systems and diagnostics, the
increased energy level in the machine, and some new safety requirements, the central safety system (cSS) has to be extended. In addition, a safety level based switchover is... -
Mr Neway Atnafu (Princeton University)05/06/2017, 13:40MagnetsPoster
A successful conceptual design was completed to develop in-vessel control coils (a.k.a. Non-Axisymmetric Control Coils or NCC). The NCC coils are a series of saddle coils that are intended to satisfy a number of physics criterion including magnetic breaking, error field control, fast Resistive Wall Mode (RWM) control and ELM stabilization. Customized Mineral Insulated Cable (MIC) was selected...
Go to contribution page -
Mr Hui Wang (Army Officer Academy)05/06/2017, 13:40Experimental devicesPoster
The motion of electron in the magnetic field from a pair of current-carrying circular coil was studied using the standard numerical method for solving the differential equations. The situations of two coils with the same and reverse directions current were studied respectively, and the results were compared.
In both of the two magnetic fields, the trajectory of an electron (or other charged...
Go to contribution page -
Dr Lei LI (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Divertors and high heat flux componentsPoster
The surface thermal flux density on the EAST divertor would reach 10MW/m2 due to improvement of heating capacity. The lower divertor as one of the main in-vessel components in EAST must be updated to fit the future experiments for achieving high performance and long pulse plasma, which aims to bridge the gaps between the high performance experimental device EAST and the Chinese Fusion...
Go to contribution page -
Nicola Pilan (Consorzio RFX)05/06/2017, 13:40Plasma heating and current drivePoster
In the framework of the program for the construction of 1 MeV–16 MW negative neutral beam injector (NNBI) for ITER, an R&D activity on voltage holding in vacuum has been initiated since 2009, aimed at supporting the design, construction, and development of the NNBI accelerator. For this purpose the voltage holding prediction model (VHPM) previously developed [1] has been updated. In the VHPM...
Go to contribution page -
Mr Xudong Wang (Institute of Plasma Physics, Chinese Academy of Science)05/06/2017, 13:40Power supply systemsPoster
The ITER Poloidal Field (PF) converter is comprised of four converter bridges, DC reactors, DC switches, etc. and most are non-standard. To evaluate the performance of these equipments, an ITER high power DC test platform has been built to carry out the rated current test and impulse current test. The latter is significant to verify the fault suppression capability of product. The DC test...
Go to contribution page -
Wang Zhaoliang05/06/2017, 13:40MagnetsPoster
The effect of gravity is Insignificant on the Conductor tension of TF coil. For The Chinese Fusion Engineering Test Reactor (CFETR), the influence is about one ten thousandth. Therefore, the design of TF coil shape generally does not consider its gravity.
Go to contribution page
The shape of the TF coil is determined by the constant-tension and without bending moment equation regardless of its gravity. By... -
Nicola Ippolito (INFN - Italy)05/06/2017, 13:40Plasma heating and current drivePoster
The Neutral Beam Injection (NBI) heating system of ITER tokamak is a key stage for the yield of the full fusion machine. The NBI yield in turn strongly depends on the performance of the first component of the system, the negative ion source of D- ions.
Go to contribution page
This negative source starts with a “driver region” where a RF discharge is induced in the deuterium gas and a plasma is created. The sources of... -
Dr Yuanyuan Ma05/06/2017, 13:40MagnetsPoster
Abstract: In the frame of CICC testing for correction coils (CC) of ITER, the soldered joint design was developed and tested up to 12kA in a loop comprising the secondary winding of a superconducting transformer. The transformer which consists of two concentric layer-wound superconducting solenoids with the primary inside secondary coil was designed and manufactured. The primary coil was wound...
Go to contribution page -
Xiang Gao (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Next step devices, DEMO, power plantsPoster
Chinese Fusion Engineering Test Reactor (CFETR) aims to bridge the gaps between the fusion experimental reactor (ITER) and the demonstration reactor (DEMO). CFETR will be designed and operated in two phases. Phase I focuses on a modest fusion power of up to 200 MW, where steady-state operation and self-sufficiency will be the two key issues. Phase II aims for DEMO validation with a fusion...
Go to contribution page -
Dr C.H. Liu (First author)05/06/2017, 13:40Plasma heating and current drivePoster
A polarization-controlled launcher has been designed for the 60 GHz electron cyclotron resonance heating system on J-TEXT. The polarizer is an essential component of the polarization-controlled launcher which is used to change the polarization of the electron cyclotron wave. The coordinate transformation method is applied for design of the polarizer with sinusoidal grooves. The polarizer was...
Go to contribution page -
Ms Soha Aslam (PPPL)05/06/2017, 13:40Project management, systems engineeringPoster
Princeton Plasma Physics Laboratory (PPPL) is a U.S. national laboratory under contract by the Department of Energy to conduct plasma physics and nuclear fusion research. With an annual budget of approximately 100 million dollars, the laboratory supports projects in various divisions such as: experimental physics, engineering, operations, IT, and facilities and infrastructure. PPPL’s Project...
Go to contribution page -
Mr Guoliang Xu (School of Nuclear Science and Technology, University of Science and Technology of China)05/06/2017, 13:40Plasma-material interactions, plasma edge physicsPoster
Since tungsten is considered as the optional divertor target material for the future fusion device, e.g. CFETR, it is crucial to keep this high-Z impurity concentration under an acceptable level to avoid significant degradation of core performance. In this work, a parameter scan study is performed to preliminarily assess the tungsten impurity. The OEDGE (OSM-EIRENE-DIVIMP) code package is...
Go to contribution page -
Sunil PAK (National Fusion Research Institute)05/06/2017, 13:40Diagnostics and instrumentationPoster
ITER has many ports to install various diagnostics which view and measure various plasma parameters. One of the ports, the upper port #18 (UP18) is designed to integrate three tenant diagnostic systems: VUV (Vacuum Ultra Violet) spectrometer, NAS (Neutron Activation System), UVNC (Upper Vertical Neutron Camera). The key design drivers for the port integration are requirements on neutron...
Go to contribution page -
Dr Shanqi Chen (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)05/06/2017, 13:40Safety and environmentPoster
Owing to their inherent safety features and lacking of high level long-lived radioactive waste, fusion power plants have long been expected to be a safe, clean and ultimate solution for human energy crisis. Among all the fusion reactors, the tokamak-type fusion power plant (FPP) with deuterium and tritium fuels is considered to be one of the most promising fusion energy systems. However, there...
Go to contribution page -
Dr Youyun Lian (Southwestern Institute of Physics)05/06/2017, 13:40Plasma facing componentsPoster
HL-2M is a new medium-sized copper-conductor tokamak device under construction at Southwestern Institute of Physics and can perform advanced divertor configurations, such as snowflake and tripod. An open cassette divertor structure with active water cooling has been designed to meet the operation requirements of HL-2M tokamak. The divertor consists of a flat-tile CFC/CuCrZr component and a...
Go to contribution page -
Mr Giuseppe Pruneri (IFMIF/EVEDA Project Team (RFX))05/06/2017, 13:40Project management, systems engineeringPoster
Progress of Auxiliary Systems for Linear IFMIF Prototype Accelerator (LIPAc)
Go to contribution page
Authors
G.Pruneri1, P.Cara2, R.Heidinger2, P.Guy2, A. Kasugai3, J. Knaster1, K. Kondo3, M.Sugimoto1, K.Sakamoto3, and the LIPAc Integrated Project Team
1IFMIF/EVEDA Project Team, Rokkasho, Japan, 2F4E, Garching, Germany, 3QST- National Institute for Quantum and Radiological Science and Technology, Rokkasho, Japan,... -
Yang Zhang05/06/2017, 13:40Divertors and high heat flux componentsPoster
Experimental advanced superconducting tokamak (EAST) is a D-shaped full superconducting tokamak device. Plasma facing components (PFCs) of divertor are most likely to be damaged during the operation, which become failure easily and have to be replaced and repaired frequently. To be able to reach the design objective, an assessment of technical risks by means of RAMI (Reliability, Availability,...
Go to contribution page -
Mr Junli Qi (University of Science and Technology of China)05/06/2017, 13:40Diagnostics and instrumentationPoster
With the construction of the next generation of large size Tokamak marked by ITER and the realization of steady state plasma discharge, the first mirror(FM) will become the core of optical elements which will be used in the optical diagnosis system of future fusion reactor. Under the action of plasma，the FM surface morphology, structure and composition, and optical properties will be changed,...
Go to contribution page -
Dr Chengzhi Cao (Southwestern Institute of Physics)05/06/2017, 13:40Plasma heating and current drivePoster
The Neutral Beam (NB) manifold is a major sub-system of ITER fueling system with complex combination pipes with the aim at distributing the working gases for NB and Diagnostic NB injector. During the final design (FD) phase, NB manifold design has been completed based on configuration management model defined to use in FD. After the FD review, the design of NB manifold suffered several design...
Go to contribution page -
Mr Qi Guo05/06/2017, 13:40Power supply systemsPoster
Due to the feasibility of analytic solution, abundant researches have been conducted to study the measurement of line current by magnetic sensor array with circular arrangement. Since the large size bus is hard to be simplified as line current, transducer with circular arrangement is no longer suitable for large current measurement, especially in power system for fusion magnet coils, which...
Go to contribution page -
Dr Huaichu Dai (1.Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China; 2. University of Science and Technology of China, Hefei 230026, China)05/06/2017, 13:40Divertors and high heat flux componentsPoster
Abstract: The Chinese Fusion Engineering Test Reactor (CFETR) is the next device in the roadmap for the realization of fusion energy in China, which aims to bridge the gaps between the fusion experimental reactor ITER and the demonstration reactor (DEMO). As a key in-vessel component in tokamak fusion reactor, the divertor which eliminates impurities, Helium ashes and heat flux often exposes...
Go to contribution page -
Jianbao WANG05/06/2017, 13:40Plasma facing componentsPoster
An active helium cooled structure was adopted in the high performance divertors, which requires metallurgical bond of plasma facing materials (PFMs) and structural materials. The tungsten materials were one important part in the PFMs, and the structural materials were made of reduced active ferritic–martensitic steels (RAFMS). The tungsten materials were joined to RAFMS using Fe-based...
Go to contribution page -
Haibiao Ji (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Materials and fabricationPoster
The 1/32 sector of CFETR vacuum vessel mock-up is welded together with four poloidal segments (PS), which are made by forming and welding. So each PS has certain machining allowance and contour error, lacks the processing datum in the process of machining welding groove. Considering each PS has complex surface profile, the method of reverse engineering is adopted to get the 3D model of each PS...
Go to contribution page -
Dr Jiangtao Jia (Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)05/06/2017, 13:40Blankets and tritium breedingPoster
Institute of Nuclear Energy Safety Technology (INEST), Chinese Academy of Sciences (CAS) is one of the leading teams undertaking its corresponding research and development and mainly responsible for structure material development and safety analysis. After the kick-off meeting for PD phase of Helium Cooled Ceramic Breeder (HCCB) Test Blanket System (TBS) held by CN DA in early 2016, safety...
Go to contribution page -
Ms Xiaoman Cheng (Institute of Plasma Physics Chinese Academy of Sciences)05/06/2017, 13:40Safety and environmentPoster
The Water Cooled Ceramic Breeder (WCCB) blanket is one of the blanket candidates for Chinese Fusion Engineering Test Reactor (CFETR). In case of in-box LOCA, the cooling channels inside the blanket module are broken, causing leakage and vaporization of the high temperature and high pressure water coolant into the Beryllium pebble beds which are used as neutron multiplier. Then the Be-steam...
Go to contribution page -
Yang Xiang (University of Science and Technology of China)05/06/2017, 13:40Tritium extraction and controlPoster
Primary concept design of CFETR (Chinese Fusion Engineering Test Reactor) has finished. In the fusion reactor, tritium is bred by lithium and then be extracted. However, tritium will contaminate the reactor structures and be leaked out to the environment eventually. For realizing the environmental friendly and tritium self-consistency, a mathematical-physical model is established to analyze...
Go to contribution page -
Yinchi Duan (Institute of Plasma physics, Chinese Academy of Sciences)05/06/2017, 13:40Power supply systemsPoster
Abstract—Based on the Experimental Physics and Industrial Control System (EPICS), a servo power controller is designed to be inserted into the existing power supply for testing its function of measurement and control in real time. The power supply controller uses double closed-loop feedback control, in which the outer-loop feedback control uses dead time modulation (DTM) technology to adjust...
Go to contribution page -
Dr Xiaoju Liu (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Plasma-material interactions, plasma edge physicsPoster
The Chinese Fusion Engineering Testing Reactor (CFETR) is the next device for the Chinese magnetic confinement fusion (MCF) program that aims to bridge the gaps between the fusion experiment ITER and the demonstration reactor DEMO. CFETR will be operated in two phases: Steady-state operation and tritium self-sustainment will be the two key issues for the first phase with a modest fusion power...
Go to contribution page -
lizhen liang (ASIPP)05/06/2017, 13:40Diagnostics and instrumentationPoster
In order to support the development of the negative ion based neutral beam injection system for next generation fusion experimental reactor, a negative ion source test facility with radio frequency source is being built at Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). A full set of spectroscopic diagnostics was designed to meet the requirement of operation performance...
Go to contribution page -
Dr Qiang Qi (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Blankets and tritium breedingPoster
Li2TiO3 is one of the most promising candidates for solid breeder materials. However, defects introduced in Li2TiO3 will affect tritium release. In the present study, vacuum-annealing defects in Li2TiO3 were investigated by means of electron spin resonance (ESR). The defects of E-centers were found to be introduced by vacuum-annealing in Li2TiO3. The color of Li2TiO3 samples becomes dark grey...
Go to contribution page -
Mrs Rongrong Luo (Southwestern Institute of Physics)05/06/2017, 13:40Materials and fabricationPoster
In this paper, 316LN austenitic stainless steel coated with plasma-sprayed alumina for low-voltage electrical insulation is reported, which used in ITER Magnent Support to prevent eddy current loops. The coating will endure the large pressure and experience the several thermel shocks under practical working environment. SEM shows that coating is dense and good adhesions with base materials,...
Go to contribution page -
Mr ZHIHONG LIU05/06/2017, 13:40Materials and fabricationPoster
Chinese Fusion Engineering Testing Reactor (CFETR) is a superconducting magnet Tokamak, The vacuum vessel (VV) will provide a high-vacuum environment for the plasma, improve radiation shielding and plasma stability and provide support for in-vessel components. The Research and Development (R&D) of the key technologies to the VV manufacture have been carried out a few years ago by Institute of...
Go to contribution page -
Wei Xu (Institute of Plasma Physics)05/06/2017, 13:40Plasma-material interactions, plasma edge physicsPoster
EAST has upgraded the upper graphite divertor to ITER-like W/Cu monoblock structure[1] with active water cooling in order to facilitate the high power and long pulse plasmas[2]. Without wall conditioning tungsten impurity accumulation has been usually observed in plasmas, which is a crucial impediment to achieving high power, long-pulse H-modes. Therefore, some wall conditioning technologies...
Go to contribution page -
Chenglian Liu (Institute of Plasma Physics, CAS)05/06/2017, 13:40MagnetsPoster
The Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) is responsible for the construction and performance testing of the 30 pairs of ITER high-temperature superconducting (HTS) current leads. A first pair of Poloidal Field (PF) coil type, 52-kA HTS current lead prototypes was built and cold tested in ASIPP in mid-2016. The test results approved their excellent performance on...
Go to contribution page -
Dr Chenglian Liu (Institute of Plasma Physics, CAS)05/06/2017, 13:40MagnetsPoster
Institute of Plasma physics, Chinese Academy of Siciencs (ASIPP) is being in charge of the the manufacturing and cold testing of the 60 single HTS current lead series production for ITER device in 2017. The norminal current for these HTS current leads are from 10 kA to 70 kA. The cold testing of all 3 types of ITER lead prototypes were qualificated by ASIPP from 2015 to 2016. This paper will...
Go to contribution page -
Dr zhiqiang zhu05/06/2017, 13:40Blankets and tritium breedingPoster
The liquid Lead Lithium (PbLi) blanket is one of the most promising blanket concepts for fusion reactors. Aiming to better develop the PbLi blanket technology and realize engineering application, key issues of PbLi blanket should be investigated such as material corrosion, the magnetohydrodynamic (MHD) effect and so on. In addition, the integrated tests and engineering design validation of...
Go to contribution page -
Ms Li Chunchun (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Plasma operation and controlPoster
For the purpose of keeping a steady-state plasma and avoiding plasma instabilities，EAST plasma control system (PCS) needs more diagnostic data produced by the EAST distributed subsystems to perform complex control algorithms. To solve the transmission problem of the above data, a real-time communication system based on MRG-Realtime (Messaging, RealTime, and Grid) operating system and...
Go to contribution page -
Dr Xiaojiao Chen (a. Institute of Plasma Physics, Chinese Academy of Science(ASIPP) b. University of Science and Technology of China)05/06/2017, 13:40Power supply systemsPoster
The International Thermonuclear Experimental Reactor (ITER) Poloidal Field (PF) power supply is consisted by thyristor-based phase-controlled converters to supply megawatt power for six PF coils. Each bridge arm of ITER PF converter is paralleled with 12 thyristors to withstand 27.5 kA rated current. For avoiding the electromagnetic interference, the trigger signals are transmitted by optical...
Go to contribution page -
Dr Lili Zhu05/06/2017, 13:40Power supply systemsPoster
Inspired by the ITER Control, Data Access and Communication (CODAC), Experimental Physics and Industrial Control System (EPICS) has been chosen for the control system. The monitoring system is a important subsystem of ITER poloidal Field(PF) Power Supply(PS) system which can real-time monitor and control PF power supply running , timely warning, abnormal positioning, support multi-user...
Go to contribution page -
Mr X. Mao05/06/2017, 13:40Materials and fabricationPoster
Abstract: Until now, the most advanced mature plasma facing unit (PFU) technology is the ITER W/Cu PFU, which is a monoblock structure composed by tungsten, copper and copper alloy (CuCrZr) as plasma facing material, interlayer and heat sink, respectively. Meanwhile copper and copper alloy play a role of structural materials in the divertor structure, on account of huge electromagnetic (EM)...
Go to contribution page -
Mr Quan Bai (SWIP)05/06/2017, 13:40Plasma-material interactions, plasma edge physicsPoster
Previous study results show that He nanobubble has great effectiveness on reducing deuterium (D) retention by acting as D diffusion barrier in undamaged commercial ITER grade tungsten (W), however, this effect on radiation damaged tungsten has not been extensively studied. In this paper, He plasma exposure (ion flux: 1023 m-2 s-1, fluence: 1025 m-2) pre-treatment was performed to create a thin...
Go to contribution page -
Dr Pengfei Zheng (Southwestern Institute of Physics)05/06/2017, 13:40Materials and fabricationPoster
Vanadium alloys, especially those with the compositions of V-4Cr-4Ti, are important candidate materials for blanket in future fusion reactors. In the past one decade, to enhance the high temperature mechanical properties, which equates with safely increasing the operation temperature, is one of the main efforts made to V-4Cr-4Ti alloys. According to dislocation theory, to properly increase...
Go to contribution page -
Mr ZIBO ZHOU (CASIPP)05/06/2017, 13:40Fueling, exhaust, and vacuum systemsPoster
The Chinese Fusion Engineering Test Reactor (CFETR) is the next generation fusion device of China for realization of fusion energy. Its mission aims to bridge the gaps between the fusion experimental reactor ITER and the demonstration reactor (DEMO). To carry out the maintenance work of CFETR, remote handling systems shall be employed. To inspect the position and status of in-vessel components...
Go to contribution page -
Yuncong Huang (Southwestern Institute of Physics)05/06/2017, 13:40Materials and fabricationPoster
Abstract：Vacuum Vessel is the main component of CFETR (China Fusion Engineering Test Reactor), a series of theoretical studies and engineering verifications should be done from the period of Vacuum Vessel structure design to analysis optimization, from manufacture and assembly process to the plasma experiment study. Notably, shells forming is relatively in the earliest phase, also one of...
Go to contribution page -
Dr Ryan Hunt (ITER Organization)05/06/2017, 13:40Plasma facing componentsPoster
ITER plasma operations begin with a limited 'first plasma', with the main purpose of concluding integrated commissioning of the tokamak. This first plasma is targeted to last at least 100 ms and with a minimum plasma current of 100 kA. As in other tokamaks, the first plasma is conducted prior to full installation of the baseline in-vessel components. Namely, the blanket and divertor are...
Go to contribution page -
Mr Liu Liang (Southwestern Institute of Physics)05/06/2017, 13:40Diagnostics and instrumentationPoster
Reliable experimental determination of the mean effective charge (Zeff) is of great importance for the impurity control in high temperature plasma. The Zeff is usually calculated using data from line integrated bremsstrahlung measurements, electron density and temperature profiles, and the plasma geometry. The visible bremsstrahlung emissivity profiles are achieved with the spatial resolution...
Go to contribution page -
Mr Desheng Cheng05/06/2017, 13:40Blankets and tritium breedingPoster
The first wall (FW) of helium gas Cooled Ceramic Breeder (HCCB) Test Blanket Module (TBM) for ITER need bear the loads like high power density heat flux from plasma, nuclear heat from neutron deposition on the structure, and the transient high heat loads like plasma disruption. The average heat flux density on FW of HCCB-TBM is about 0.3MW/m2 and the maximum partial transient heat flux may...
Go to contribution page -
Dr Lei Cao (Institute of plasma physics, Chinese Academy of Science)05/06/2017, 13:40Divertors and high heat flux componentsPoster
The design of divertor is one of the most challenges for CFETR as the max heat flux on the CFETR divertor would be more than 20MW/m2 and the max plasma current is 1MA. Surface and structural damage to divertor due to the frequent loss of plasma confinement remains a serious problem for the tokamak reactor concept. The deposited plasma energy during major disruptions, edge-localized modes...
Go to contribution page -
jian ge (asipp)05/06/2017, 13:40Diagnostics and instrumentationPoster
Radial x-ray camera (RXC) is an important diagnostic device in the International Thermonuclear Experimental Reactor (ITER) tokamak. The function of x-ray camera is to provide a measurement of soft X-ray emission from plasma, which is necessary for the operation and control of plasma to support key physics researches. As a key device to measure the plasma in tokamak, it is required to meet the...
Go to contribution page -
Dr Zhongwei Wang05/06/2017, 13:40Fueling, exhaust, and vacuum systemsPoster
The function of the cryo-vacuum pump (CVP) system is basically the control of the plasma density by condensing undesirable gases together with a set of turbo molecular pumps. One CVP will be installed under each of the 10 units of the actively cooled divertor in Wendelstein7-X for the long pulse operation up to 30 minute duration scheduled in 2020. The 10 CVPs are independent and each one is...
Go to contribution page -
Mr Xingli Wang (Institute of Plasma Physics, Chinese Academy of Sciences)05/06/2017, 13:40Diagnostics and instrumentationPoster
Tungsten divertor is one of the most important plasma facing components in EAST device. However, it has complex structure and faces extreme work environment. Centralized thermal strain would cause leakages on some weak welding seams, which was harmful for divertor’s operation. To measure divertor’s thermal strain shall be a valued way to understand its service behavior and then optimize its...
Go to contribution page -
Mrs Shiying HE (Institute of Plasma Physics, CAS)05/06/2017, 13:40Power supply systemsPoster
This paper describes architecture and characteristics of time synchronization network of EAST poloidal field power supply control system. After analyzing the characteristics of IEEE 1588, the paper points out the advantages of IEEE 1588 and choses it as the implementation protocol for time synchronization network in EAST poloidal field power supply control system. With this method, a master...
Go to contribution page -
Prof. GE LI (Inst. of Plasma Physics, CAS)05/06/2017, 13:40Experimental devicesPoster
The size scaling is recently developed by Costley, Hugill and Buxton (CHB) for seeking highest tokamak performance within physics limits at fixing the fraction of Greenwald density limit fGW, normalized plasma pressure βN, and fusion power Pf by scanning device-major-radius, R. The size-cancelling effects of the density limit are found in the fusion triple product of Lawson criterion, nTτE and...
Go to contribution page -
Dr Hua Li (Institute of Plasma physics, Chinese Academy of Sciences)05/06/2017, 13:40Power supply systemsPoster
The China fusion engineering test reactor (CFETR) could output 50~200 MW fusion power for demonstrating power generation. The overall structure of fusion power plant in concept design is similar to a pressurized-water reactor (PWR), except a double-fed induction generator with flywheel (DFIGF) has been proposed to replace the traditional synchronous generator used in a PWR. The heat source of...
Go to contribution page -
Mr Hao Wang (School of Mechanical Engineering, Hangzhou Dianzi University，Hang Zhou, China)05/06/2017, 13:40Blankets and tritium breedingPoster
The study of magnetohydrodynamic (MHD) flow is important in the application of the liquid metal blankets in thermal nuclear fusion reactors. Hunt presented an analytical solution of the conducting fluid flow in a rectangular duct under a uniform transverse magnetic field with insulating walls parallel to the magnetic field and thin walls with arbitrary conductivity perpendicular the magnetic...
Go to contribution page -
Mr Dingyu Lao (Institute of Plasma Physics Chinese Academy of Sciences (ASIPP))05/06/2017, 13:40Tritium extraction and controlPoster
Tungsten and RAFM steel are respectively used as armor material of first wall (FW) and structure material. The Li2TiO3/Be12Ti mixed pebble bed is selected to fulfill tritium breeding for water-cooled ceramic blanket (WCCB) in China Fusion Engineering Test Reactor (CFETR). Tritium would be existed in all materials of the blanket because of its diffusivity and permeability. Thus, it is crucial...
Go to contribution page -
Mr Pengfei Zi ( Institute of Plasma Physics Chinese Academy of Sciences)05/06/2017, 13:40Divertors and high heat flux componentsPoster
EAST is one of the most important experimental fusion devices of China, the design of each component has important reference significance for China Fusion Engineering Testing Reactor (CFETR). Divertor, as one of the most important in-vessel components on the EAST, has always been quite difficult and challenging for its design. With the completion of the upgrade of the upper divertor, EAST has...
Go to contribution page -
Andrius Tidikas (Lithuanian Energy Institute)05/06/2017, 13:40Blankets and tritium breedingPoster
One of the conceptual designs of the breeder blanket for a European DEMO is the Water Cooled Lithium Lead (WCLL) concept. Design development of the WCLL blanket in recent years has led to evolution of the neutronics model employing the MCNP code, with key changes in radial lengths and thickness as well as dimensional differences in inner structures such as breeding zone, shielding zones and...
Go to contribution page
Choose timezone
Your profile timezone: