DOCSLIB.ORG

M Ono Presentation ICEF 2016 V4.Pptx

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text

Load more

Spherical Tokamak for Economical Fusion Energy Development Masayuki Ono NSTX-U Department Head PPPL, Princeton University PPPL Innovation for Cool Earth Forum October 5 - 6, 2016 M. Ono ICEF 2016 October 5, 2016 Fusion for safe limitless energy source Fusion could provide energy for Energy 10 million times that of fossil fuel by weight future mankind: D + T He4 + n + 17.6 MeV - Environmentally friendly Heat from fusion reactor can also produce hydrogen! - Safe - Globally abundant fuel - High energy density - Support hydrogen economy Global Warming Nuclear spent fuel A large asteroid / comet hit Earh 65 million years ago Annual CO2 release – 40 billion tons Still increasing 8,000 tons per year M. Ono ICEF 2016 October 5, 2016 2 Fusion for safe limitless energy source Fusion can also solve potential challenges for humanity Fusion could provide energy for Energy 10 million times that of fossil fuel by weight future mankind: D + T He4 + n + 17.6 MeV - Environmentally friendly Heat from fusion reactor can also produce hydrogen! - Safe - Globally abundant fuel - High energy density - Support hydrogen economy Fusion could help solve future challenges facing mankind: - Global warming - Fission reactor spent fuel - Space travel Global Warming Nuclear spent fuel A large asteroid / comet hit Earh 65 million years ago Annual CO2 release – 40 billion tons Still increasing 8,000 tons per year M. Ono ICEF 2016 October 5, 2016 3 Nuclear Fusion has many possible approaches Many Types of Magnetic Bottles! Beta is a ratio of plasma pressure over magnetic pressure - Plasma pressure produces fusion power - Mangetic pressure provided by coils but cost $ Tokamak Tri-Alpha NSTX-U Energy (Private) (US-DOE) A Modern Conventional Spherical (Private) Compact Stellarator Tokamak Tokamak Toroids Very Low B Axi-symmettric High beta Ip / IC ~ 0 Ip / IC ~ 0.1 Ip / IC ~ 1 Ip / IC > 1 LHD, W7-X TFTR, JET, JT-60, ITER NSTX, MAST. MST, RFX Ip = plasma current helps plasma confinement and stability Ic = coil current also helps plasma confinement and stability but cost $ M. Ono ICEF 2016 October 5, 2016 4 Nuclear Fusion has many possible approaches Many Types of Magnetic Bottles! What is the best fusion approach? Higher beta*, smaller size, lower field, economical Tokamak Tri-Alpha NSTX-U Energy (Private) (US-DOE) A Modern Conventional Spherical (Private) Compact Stellarator Tokamak Tokamak Toroids Very Low B Axi-symmettric High beta Ip / IC ~ 0 Ip / IC ~ 0.1 Ip / IC ~ 1 Ip / IC > 1 Enable more external control *Beta is a ratio of plasma pressure over magnetic pressure M. Ono ICEF 2016 October 5, 2016 5 Princeton Plasma Physics Laboratory PPPL investigates many type of magnetic bottles and plasma applications Model A, B C-Stellarator ST, ACT, PLT, PDX, PBX TFTR NSTX NSTX-U Matterhorn1960 1970 1980 1990 2000 2010 1951 Stellarators Conventional Tokamaks 10 MW Spherical Tokamaks Princeton U I joined Fusion Fusion Lab. Atoms for the lab Peace 1958 Power TFTR Tokamak NSTX Spherical Tokamak A Modern Stellarator Conventional Tokamak Spherical Tokamak Axi-symmettric High beta M. Ono ICEF 2016 October 5, 2016 6 A spherical tokamak (ST) is a high beta tokamak Favorable average curvature improves stability at high beta 2 Aspect Ratio A = R /a Elongation κ = b/a Toroidal Beta βT = 〈p〉 / (BT0 / 2µ0) Camera image from NSTX-U Tokamak ST A ~ 3, A ~ 1.5, κ = 1.5-2, κ = 2-3, q95 = 3-4, q95 = 8-12, βT = 3-10% βT = 10-40% M. Ono ICEF 2016 October 5, 2016 7 Operating ST Research Facilities Since 2000 NSTX and MAST: MA-class STs, Smaller STs addressing topical issues NSTX, USA PEGASUS, USA LTX/CDX-U, USA GLOBUS-M, Russia MAST, UK HIST, Japan LATE, Japan TST-2, Japan UTST, Japan R0 ~ 0.75 m QUEST/CPD, Japan R0 ~ 0.85 m VEST, Korea HIT-II, USA GLOBUS-M PEGASUS QUEST HIT-II MAST z KTM HIST ST25(HTS) SUNISTVEST z NSTX/LTX LATE TST-2 TS3/4 UTST TS3/4, Japan SUNIST, China ETE, Brazil ST25, UK ETE STs operated since 2000 z M. Ono ICEF 2016 October 5, 2016 8 NSTX-U Facility Came On Line This year To demonstrate fully sustained high beta plasmas nd 2 NBI 1st NBI HHFW System NSTX-U M. Ono ICEF 2016 October 5, 2016 9 Unique ST properties support and accelerate a range of development paths toward fusion energy Extend Predictive Capability for ITER and Burning Plasma Physics - Toroidal Science ITER High β physics, rotation, shaping for MHD, transport Non-linear Alfvén modes, fast-ion dynamics, Electron gyro-scale turbulence at low ν* M. Ono ICEF 2016 October 5, 2016 10 Higher βT enables economical fusion power and compact neutron sources for near term and long term applications 2 Pfusion ∝ 〈p〉 x Vol Data base from START, MAST, PEGASUS and NSTX βN = 6 40 2 4 5 Pfusion ∝ βT BT0 x Vol 4 (%) β ST-FNSF Investment Product Physics 3 cost 20 Knob Toroidal Tokamak 2 ITER Higher β allows lower BT0 and/or smaller Vol both lower cost 0 0 4 8 Ip/aBT0 (MA/mT) Note: Ultra high β STs ~ Lower BT0 Lower Cost, Greater Safety, and 50% produced in TS-3 Reliability Device at Univ. Tokyo M. Ono ICEF 2016 October 5, 2016 11 0.0 0.2 0.4 0.6 0.8 1.0 -1 log10(disruptivity [s ]): N -0.5 -0.25 0.0 0.25 0.5 0.75 1.00 0.0 0.2 0.4 a)0.6 0.8 1.0 6 N β 4 NSTX Data Demonstrates a Favorable Operations Window At 2 High β For Reduced Disruptivity in an ST-FNSF -1 Good!35237log 10total(disruptivity samples [s ]): 2 3 4 5 6 N -0.5 -0.25 0.0 q*0.25 0.5 0.75 1.00 a) STb) 6 reactors 6 S=37 S=20 N β 4 N β 4 2 2 35237 total samples 1.5 2.0 2.5 3.0 3.5 4.0 35237 total samplesp0/<p> • No strong increase in disruptivity as βN increases 10 20 30 40b) S • Reduction in disruptivity also with: 6 (S=q95IP/aBT) • Decreasing li (broader current profile) Example: Disruptivity is reduced • Decreasing pressure peaking N β 4with strong shaping of the Upgrades will test and improve these plasma boundary. favorable trends in a systematic way 2 S.P. Gerhardt et al., NF (2013) 35237 total samples M. Ono ICEF 2016 October 5, 2016 12 0.4 0.6 0.8 1.0 1.2 li Understanding Electron Energy Confinement is Critical for Reactor Design Energy Diffusivity or Rate of Energy Loss Electron energy is NSTX escaping from fusion plasma core much faster (much more than 10x) than neoclassical prediction – anomalous! Ion energy is escaping from fusion plasma core not much faster than neoclassical prediction • Fusion Alpha-particle energy mainly heats electrons • If electron energy loss is rapid, alpha-heating cannot keep fusion going Y. Ren. M. Ono ICEF 2016 October 5, 2016 13 Encouraging Confinement Trend with Collisionality in STs Important implications for future STs if trend continues NSTX MAST Increasing confinement Increasing electron temperature Increasing electron temperature S.M. Kaye et al., NF(2013) M. Valovic et al., NF (2011) M. Ono ICEF 2016 October 5, 2016 14 Favorable confinement trends with Te and β help make economical compact fusion reactors Fusion triple product = n τ T • Conventional energy confinement time τ improves with device size (or volume) and magnetic field. But the cost increases with V and B. • ST scaling suggests confinement improvement can be achieved with increased temperature which is Hot achieved in reactor naturally for Plasma Core free. • Improved confinement could lead to smaller volume more economical fusion reactor • Better confinement could also enable small neutron sources which have many applications NSTX-U Micro-tearing simulation by W. Guttenfelder and F. Scotti M. Ono ICEF 2016 October 5, 2016 15 Favorable confinement trend with collisionality and β found in ST experiments -0.8 -0.0 ST scaling observed in NSTX and MAST: τE, th ∝ ν*e β -0.1 -0.9 Tokamak empirical scaling (ITER 98y,2): τE, th ∝ ν*e β Surprising confinement scaling in STs! Confinement time actually increased with temperature while previous scaling Lithium predicted just the Reactor Boron opposite! regimes Increasing Te Also no confinement degradation observed in ST with plasma β M. Ono ICEF 2016 October 5, 2016 16 Several ST Fusion Power Plants Design Studied Low Toroidal Field and Magnetic Energy ARIES-ST JUST Cu Power Plant SC ST Power Plant R0 ~ 3.2 m R0 ~ 4.5m BT0 ~ 2.1T BT0 ~ 2.36T F. Najmabadi et al., FED (2003) Y. Nagayama et al., IEEJ (2012) H. R. Wilson, et al., NF (2004) B.G. Hong, Yet al.,NF (2011) K. Gi NF (2015) 17 M. Ono ICEF 2016 October 5, 2016 ST Fusion Plant Designed With High Temperature SC A=2, R0 = 3m HTS-TF FNSF / Pilot Plant BT = 4T, IP = 12.5MA κ = 2.5, δ = 0.55 βN = 4.2, βT = 9% H98 = 1.8, HPetty-08 = 1.3 fgw = 0.80, fBS = 0.76 Startup IP (OH) ~ 2MA 2 JWP = 70MA/m BT-max = 17.5T No joints in TF Vertical maintenance Pfusion = 520 MW PNBI = 50 MW, ENBI = 0.5MeV QDT = 10.4 Qeng = 1.35 Pnet = 73 MW 2 〈Wn〉 = 1.3 MW/m Peak n-flux = 2.4 MW/m2 Peak n-fluence = 7 MWy/m2 J. Menard et al., NF (2016) by PPPL, …Tokamak Energy M. Ono ICEF 2016 October 5, 2016 18 Fusion to Solve Fusion Waste Material Problem Only a Compact Fusion ST Cores Needed For Neutron Production Tritium ST Fusion-Fission Hybrid Lithium ST Heat, Electricity 50 – 100 MW Fusion Fission 1 – 3 GWt Core Spent Fuel 100 MW 14 MeV Fission Fuel Fusion neutrons World is full of spent fuel from fission reactors – 20 t per year per reactor – 76,000 t just in the USA • High energy fusion neutrons can break down the spent fuel further to reduce long live isotopes from fission spent fuel, e.g., Pu242, Am243, Cm244 and Cm246.
Recommended publications
  • The Fifth A3 Foresight Workshop on Spherical Torus

    The Fifth A3 Foresight Workshop on Spherical Torus

    The Fifth A3 Foresight Workshop on Spherical Torus Feb. 15-17, 2017 Fontaine Blanche Hotel (丽水云泉大酒店), Kunming, Yunnan, China Organized by: Tsinghua University Yunnan Normal University Sponsors: National Natural Science Foundation of China (NSFC) Japan Society for the promotion of Science (JSPS) National Research Foundation of Korea (NRF) Agenda Presentation type: 30 min =25 min talk +5 min discussion 20 min =15 min talk +5 min discussion Tuesday, February 14, 2017 (Day 0, the lobby of the hotel) 14:00-17:30 Registration Wednesday, February 15, 2017 (Day 1, Yuntu Hall) 8:30-9:00 Registration 9:00-9:20 Opening President of Yunnan Normal University Prof. Z. Gao (Tsinghua U, China) Prof. Y. S. Hwang (Seoul National U, Korea) Prof. M. Inomoto (U Tokyo, Japan) 9:20-10:20 Session 1 Chair: GAO Zhe 9:20-9:50 Overview of VEST Prof. HWANG Yong Seok 9:50-10:20 Overview of UTST Prof. INOMOTO Michiaki 10:20-10:40 Coffee Break and Photo 10:40-11:40 Session 2 Chair: MAEKAWA Takashi 10:40-11:10 Overview of SUNIST Prof. GAO Zhe 11:10-11:40 Overview of TST-2 Prof. EJIRI Aira 11:40-13:40 Lunch 13:40-16:00 Session 3 Chair: RYU Chang Mo 13:40-14:10 Non-inductive startup studies on LATE Prof. MAEKAWA Takashi 14:10-14:40 Overview of TBM Program in ITER Prof. HONG Bong Guen 14:40-15:00 Fundamental Concept of High Field Side Mr. ELSERAFY Hatem injection of RF for EBW excitation in QUEST 15:00-15:20 Intermittent Plasma Bursts in Over-dense Mr.
  • Physique Nucléaire Et De L'instrumentation Associée Introduction

    Physique Nucléaire Et De L'instrumentation Associée Introduction

    FR0108546 # DEA-DAPNIA-RA-1997-98 A il. ..33/04 -DSM Département d'Astrophysique, de physique des Particules, de physique Nucléaire et de l'Instrumentation Associée Introduction Motivés par la curiosité pour les connaissances fondamentales et soutenus par des investissements impor- tants, les chercheurs du vingtième siècle ont fait des découvertes scientifiques considérables, sources de retombées économiques fructueuses. Une recherche ambitieuse doit se poursuivre. Organisé pour déve- lopper les grands programmes pour le nucléaire et par le nucléaire, le CEA est bien armé pour concevoir et mettre au point les instruments destinés à explorer, en coopération avec les autres organismes de recherche, les confins de l'infiniment petit et ceux de l'infinimenf grand. La recherche fondamentale évolue et par essence ne doit pas avoir de frontières. Le Département d'astrophysique, de physique des particules, de physique nucléaire et de l'instrumentation associée (Dapnia) a été créé pour abolir les cloisons entre la physique nucléaire, la physique des particules et l'as- trophysique, tout en resserrant les liens entre physiciens, ingénieurs et techniciens au sein de la Direction des sciences de la matière (DSM). Le Dapnia est unique par sa pluridisciplinarité. Ce regroupement a permis de lancer des expériences se situant aux frontières de ces disciplines tout en favorisant de nou- velles orientations et les choix vers les programmes les plus prometteurs. Tout en bénéficiant de l'expertise d'autres départements du CEA, la recherche au Dapnia se fait princi- palement au sein de collaborations nationales et internationales. Les équipes du Dapnia, de I'IN2P3 (Institut national de physique nucléaire et de physique des particules) et de l'Insu (Institut national des sciences de l'Univers) se retrouvent dans de nombreuses grandes collaborations internationales, chacun apportant ses compétences spécifiques afin de renforcer l'impact de nos contributions.
  • SUNIST Spherical Tokamak

    SUNIST Spherical Tokamak

    rd th SUNISTSUNIST The 3 IAEA TCM on Spherical Torus and the 11 STW, St. Petersburg Preliminary experiment of plasma current startup by ECR wave on SUNIST spherical tokamak HE Yexi, ZHANG Liang, *FENG Chunhua, FU Hongjun, GAO Zhe, TAN Yi, WANG Wenhao, *WANG Long, *YANG Xuanzong, XIE Lifeng [email protected], 86-10-62791874 (o), 86-10-62782658 (fax) SUNIST United Laboratory Department of Engineering Physics, Tsinghua University, Beijing 100084, P.R.China *Institute of Physics, Chinese Academy of Science, Beijing 100080, P.R.China This work was supported by JSPS-CAS Core-University Program on Plasma and Nuclear Fusion, the National Nature and Science Fund of China (Grant numbers: 10275041 and 10375089) , and International Atomic Energy Agency (Research contract No. 12935/R0) . SUNIST- Sino UNIted Spherical Tokamak UNISTSUNISTUNISTSUNIST OUTLINE SUNIST spherical tokamak Preliminary result Remained questions UNISTSUNISTUNISTSUNIST SUNIST spherical tokamak SUNIST United Laboratory SUNIST United Laboratory founded in 2004, consists of Department of Engineering Physics, Tsinghus University (DEP) ; Institute of Physics, Chinese Academy of Science (IOP) and keeping very close collaboration with Southwestern Institute of Physics (SWIP) and Institute of Plasma Physics, Chinese Academy of Science (IPPAS). Members of SUNIST Laboratory He, Yexi Department of Engineering Physics, Tsinghua University, Beijing 100084, P.R.China, 86-10- 62791874(lab), 86-10-62782658(fax), [email protected] (e-mail) Yang, Xuanzong Institute of Physics,
  • Topical Review Solenoid-Free Plasma Start-Up in Spherical Tokamaks

    Topical Review Solenoid-Free Plasma Start-Up in Spherical Tokamaks

    Home Search Collections Journals About Contact us My IOPscience Solenoid-free plasma start-up in spherical tokamaks This content has been downloaded from IOPscience. Please scroll down to see the full text. 2014 Plasma Phys. Control. Fusion 56 103001 (http://iopscience.iop.org/0741-3335/56/10/103001) View the table of contents for this issue, or go to the journal homepage for more Download details: IP Address: 198.125.233.17 This content was downloaded on 06/01/2015 at 20:20 Please note that terms and conditions apply. Plasma Physics and Controlled Fusion Plasma Phys. Control. Fusion 56 (2014) 103001 (19pp) doi:10.1088/0741-3335/56/10/103001 Topical Review Solenoid-free plasma start-up in spherical tokamaks R Raman1 and V F Shevchenko2 1 William E. Boeing Department of Aeronautics and Astronautics, University of Washington, Seattle, WA 98195, USA 2 CCFE, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK E-mail: [email protected] Received 15 June 2014, revised 20 August 2014 Accepted for publication 1 September 2014 Published 22 September 2014 Abstract The central solenoid is an intrinsic part of all present-day tokamaks and most spherical tokamaks. The spherical torus (ST) confinement concept is projected to operate at high toroidal beta and at a high fraction of the non-inductive bootstrap current as required for an efficient reactor system. The use of a conventional solenoid in a ST-based fusion nuclear facility is generally believed to not be a possibility. Solenoid-free plasma start-up is therefore an area of extensive worldwide research activity.
  • UST 1 Stellarator and Status of the 3D Printed UST 2 Stellarator* on Leave of Absence Vicente from NFL, Queral CIEMAT L 1 Outline

    UST 1 Stellarator and Status of the 3D Printed UST 2 Stellarator* on Leave of Absence Vicente from NFL, Queral CIEMAT L 1 Outline

    UST_1 stellarator and Status of the 3D printed UST_2 stellarator Vicente M. Queral * Talk given in Columbia University, New York, NY, USA 1st October 2013 TM UST_1 stellarator and status of the 3D printed UST_2 stellarator* On leave of absence Vicente from NFL, Queral CIEMAT L 1 Outline Background Basic UST_1 and UST_2 data Design, construction and results in UST_1 ▪ Conceptual design of UST_1 ▪ Engineering design. Development of a construction method ▪ Validation of the construction method and design ▪ Results and conclusions Status of the 3D printed UST_2 stellarator ▪ Experimental validation of engineering concepts ▪ Conceptual design ▪ UST_2 engineering design. Fabrication tests ▪ Future work UST_1 stellarator and status of the 3D printed UST_2 stellarator Vicente Queral L 2 Background ► I am on a leave of absence period from the National Fusion Laboratory, CIEMAT, Spain. ► I worked in CIEMAT for almost 5 years, in Remote Handling, for IFMIF (International Fusion Materials Irradiation Facility), ITER and DEMO. ► Up to now, I have developed the work on stellarators on my own, with personal funds (for three years before CIEMAT work, at nights and weekends during CIEMAT work, and now 1.5 years during the leave of absence), with some help and contribution from CIEMAT. ► The work is R&D and innovation in engineering, focused in new construction methods for stellarators. It is not focused on physics and plasma experiments. UST_1 stellarator and status of the 3D printed UST_2 stellarator Vicente Queral L 3 Basic UST_1 data UST_1 modular stellarator • UST_1 stellarator was designed, built and operated from 2005 to 2007 in my personal laboratory. • Cost of the whole facility ~ 3000 € (many 2nd hand pieces).
  • RFP Program Started in China

    RFP Program Started in China

    6th US-PRC Magnetic Fusion Collaboration Workshop San Diego, July 10-12, 2012 Physics Rationale and Engineering Design of Keda Torus eXperiment Wandong Liu, on behalf of KTX team School of Physical Sciences University of Science and Technology of China Collaboration with： – Institute of plasma physics – University of Wisconsin at Madison, U.S. – South western institute of physics – Consorzio RFX, Padova, Italy – Huazhong University of Science and Technology – Kyoto Institute of Technology, Japan – University of California Los Angles, U.S. – University of Saskatchewan, Canada A new RFP program started in China The new reversed field pinch（RFP） program in China, Keda Torus eXperiment （KTX）officially started by the Ministry of Science and Technology, in the framework of the ITER domestic program The duration of the program is 3 years, starting from the end of last year for design and construction of the machine (2012-2014) The University of Science and Technology of China (USTC) will provide a new building to accommodate KTX device Reversed Field Pinch: an important alternate toroidal concept Three major configuration of MCF Stellarator: magnetic field is generated totally by the external coils Tokamak: magnetic field is generated primarily by the external coils RFP: magnetic field is generated primarily by the plasma current Tokamak RFP Main advantages of Reversed Field Pinch Small externally applied field: the use of normal magnets, high engineering beta, high mass-power-density, efficient assembly Large plasma current density:
  • Observation of Multiple Shear Layers and Long-Range Transport Events on HL-2A Tokamak Wenbin Liu1, George R

    Observation of Multiple Shear Layers and Long-Range Transport Events on HL-2A Tokamak Wenbin Liu1, George R

    MF-O9 AAPPS-DPP2019 3rd Asia-Pacific Conference on Plasma Physics, 4-8,11.2019, Hefei, China Observation of multiple shear layers and long-range transport events on HL-2A tokamak Wenbin Liu1, George R. Tynan2,3, Yihang Chen3, Rui Ke3, Yifan Wu3, Zengchen Yang3, Kairui Fang3, Weiwen Xiao4, Min Xu3, Zhe Gao1 and HL-2A team3 1Department of engineering physics, Tsinghua University 2Department of Mechanical and Aerospace Engineering, University of California, San Diego 3Center for Fusion Science, Southwestern Institute of Physics 4Department of Physics, Zhejiang University e-mail (speaker): [email protected] Recent flux-driven gyrokinetic computational shown in Fig. 1 (b). modeling and theory suggested the existence of an 푬 × 푩 4. Multi-channel ECE and FMCW reflectometry staircase in the plasma core consisting of a series of data show that there are some corrugations in the m/n=0/0 푬 × 푩 shear layers formed at different plasma background gradient profiles and their radial positions are minor radii via the action of the turbulent Reynolds consistent with those of the shear layers; stress1,2. These layers then act as semi-permeable 5. Moreover, In the region between these shear transport barriers and thus regulate the background layers, transport events with long radial distance and small gradients, causing a localized steepening of the gradient. radial wavenumber satisfy the characteristics of avalanche Recent published experimental work in TORE-SUPRA dynamics; shows that the turbulent radial correlation length exhibits 6. A statistical result shows that the weak a number of marked reductions across the minor radius of disturbances terminate at the shear layers while strong the device, and data also suggest that the turbulent eddies disturbances penetrate the shear layers, thus verifies the undergo a reversal of their anisotropic tilting as these semi-permeability of the shear layers which is an minima are traversed.
  • Recent Progress in the SUNIST Spherical Tokamak

    Recent Progress in the SUNIST Spherical Tokamak

    The Joint Meeting of 5th IAEA Technical Meeting on Spherical Tori, 16th International Workshop on Spherical Torus (ISTW2011), and 2011 US-Japan Workshop on ST Plasma September 27-30, 2011 , National Institute for Fusion Science, Toki, Japan Recent Progress in the SUNIST Spherical Tokamak Yi Tan1, Zhe Gao1, Wenhao Wang1, Lifeng Xie1, Long Zeng1, Huiqiao Xie1, Ou Zhao1, Yangqing Liu1, Yanzheng Jiang1, Song Chai1, Xiaowei Peng1, Kun Yao1, Aihui Zhao1 Chunhuan Feng2, Long Wang2, Xuanzong Yang2 Guixiang Yang3 Email: [email protected] 1) Department of Engineering Physics, Tsinghua University, Beijing, China 2) Institute of Physics, Chinese Academic of Science, Beijing, China 3) College of Nuclear Physics and Technology, Nanhua University, Hengyang, China This work is supported by the Major State Basic Research Development Program from MOST of China under Grant No. 2008CB717804, 2009GB105002 and 2010GB107002, NSFC under Grant No. 10990214, 10775086 and 11005066. Introduction to SUNIST • SUNIST: Sino UNIted Spherical Overview of the SUNIST device Tokamak – What are united? • Department of Engineering Physics, Tsinghua University • Institute of Physics, Chinese Academy of Sciences – Major parameters • R0/a: 0.3/ 0.23m ~ 1.3 • BT0: <0.15 T • IP: ~ 50 kA 19 -3 • ne: ~ 110 m – Major diagnostics • Langmuir probes • Normal ( <100 kHz) / High frequency (~1 MHz) magnetic probes • Visible Spectrometers (250~ 750 nm) • 94 GHz interferometer • 8 mm reflectometer • Fast visible camera • Ha diode array Section view of the The vacuum SUNIST device vessel of
  • Physics and Computational Simulations of Plasma Burn-Through for Tokamak Start-Up

    Physics and Computational Simulations of Plasma Burn-Through for Tokamak Start-Up

    Imperial College London Department of Physics Physics and Computational Simulations of Plasma Burn-through for Tokamak Start-up Hyun-Tae Kim Submitted in part fulfilment of the requirements for the degree of Doctor of Philosophy in Physics of Imperial College London, July 2013 Abstract This thesis will discuss the fundamental process of high temperature plasma formation, con- sisting of the Townsend avalanche phase and the subsequent plasma burn-through phase. By means of the applied electric field, the gas is partially ionized by the avalanche process. In order for the electron temperature to increase, the remaining neutrals need to be fully ionized in the plasma burn-through phase, as radiation is the main contribution to the electron power loss. The radiated power loss can be significantly affected by impurities resulting from inter- action with the plasma facing components. The parallel transport to the surrounding walls is determined by the so called connection length in the plasma. Previously, plasma burn-through was simulated with the assumptions of constant particle con- finement time and impurity fraction. In the new plasma burn-through simulator, called the DYON code, the treatment of particle confinement time is improved with a transonic ambipo- lar model for parallel transport, by using the effective connection length determined by the magnetic field lines, and Bohm diffusion model for perpendicular transport. In addition, the dynamic evolution of impurity content is calculated in a self-consistent way, using plasma wall interaction models. The recycling of the particles at the walls is also modelled. For a specific application, the recent installation of a beryllium wall at Joint European Torus (JET) enabled to investigate the effects of plasma facing components on plasma formation and build-up of plasma current in the device.
  • Preparation and Submission of a Manuscript for the Proceedings

    Preparation and Submission of a Manuscript for the Proceedings

    1 EX/P4-47 Re-commissioning of the Spherical Tokamak MEDUSA in Costa Rica V.I. Vargas1, J. Mora1, L.A. Araya-Solano1, A.M. Rojas-Loaiza1, J.M. Arias-Brenes1, J. F. Rojas1, J.I. Monge1, A. Canizales1, E. Acuña1, N. Piedra-Quesada1 1Instituto Tecnológico de Costa Rica (ITCR), Cartago, Costa Rica E-mail contact of main author: [email protected] Abstract. The low aspect ratio spherical tokamak (ST) MEDUSA (Madison EDUcation Small Aspect ratio tokamak) is currently being re-commissioned in Costa Rica and was donation to Costa Rica Institute of Tecnology by University of Wisconsin-Madison, USA. The major characteristics of this device are: plasma major radius Ro < 0.14 m, plasma minor radius a < 0.10 m, plasma vertical elongation 1.2, toroidal field at the 20 -3 geometric center of the vessel BT < 0.5 T, plasma current Ip < 40 kA, ne (0) < 2 x 10 m , central electron temperature Te (0) < 140 eV, discharge duration is < 3 ms, top and bottom rail limiters, natural divertor D-shaped ohmic plasmas). In addition to training, the major objective of renamed device MEDUSA-CR is to address relevant physics for spherical and conventional tokamaks, taking advantage of the insulating vessel which allows plasma real time response to applied external electrical or magnetic fields. The major topics for the scientific programme are 1) Comparative studies of equilibrium and stability between natural divertor D and bean-shaped ST plasmas; 2) Study of an ergodic magnetic limiter; 3) Alfvén wave heating and current drive and; 4) Transport. Advances in some of these topics will be presented in this work, in addition to the technical tasks of machine re-commissioning involving the re-design of energy, gas injection, vacuum system and control systems.
  • Soltan Institute for Nuclear Studies Annual Report 1995

    Soltan Institute for Nuclear Studies Annual Report 1995

    ISSN 1232-5309 SOLTAN INSTITUTE FOR NUCLEAR STUDIES INSTYTUT PROBLEMdW JADROWYCH im. A. SOtTANA PL9701895 ANNUAL REPORT 1995 Otwock - Swierk 19 9 6 ISSN 1232-5309 SOLTAN INSTITUTE FOR NUCLEAR STUDIES ANNUAL REPORT 1995 Editors: E. Infeld M. Jaskdla P. Zuprariski PL-05-400 OTWOCK-SWIERK, POLAND Tel: 048-22-779 8948 Telex: 813244 IBJ swpl Fax: 048-22-779 3481 E-mail: [email protected] Otwock - Swierk 1996 Technical Editor: Krystyna Traczyk Technical Staff: Jolanta Falkowska Danuta Szczepaniak The Report was printed using a Word Perfect 6,0 word processor on a PC 486/40 and a Hewlett Packard LaserJet 5P SINS Annual Report 1995 1 ABSTRACT: This report surveys our activities in the following fields: nuclear, particle and cosmic ray physics, plasma and thermonuclear research and techniques, nuclear electronics, accelerator techniques and physics, as well as ionizing radiation detection and spectrometry techniques, developmental work and implementations resulting from chosen trends in nuclear physics* 1. STRESZCZENIE: Raport roczny Instytutu Problemdw Jqdrowych im. A.Sottana przedstawia zwi$zfy przeglqd badan teoretycznych, doswiadczalnych, technologicznych i technicznych z dziedziny fizyki jqdrowej, promieniowania kosmicznego, fizyki czqstek elementarnych, fizyki plazmy, elektroniki jqdrowej, detektorow gazowych i pdfprzewodnikowych, fizyki i techniki akceleratorow, fizyki oslon przed promieniowaniem i mikrodozymetrii" 1. *) This work was supported in part by the State Committee for Scientific Research in Poland, Decision Nr 621/E-78/S/95 **) Badania byiy finansowane glownie przez Komitet Badan Naukowych w Polsce wedfug Decyzji Nr 621/E-78/S/95 2 SINS Annual Report 1995 CONTENTS FOREWORD............................................................................................................................................. 3 I. GENERAL INFORMATION........................................................................................................ 5 II. MANAGEMENT OF THE INSTITUTE..............................
  • Sf: Su Signature Analysis • Simulated Annealing • Sine Anno • S: Distance

    Sf: Su Signature Analysis • Simulated Annealing • Sine Anno • S: Distance

    StarBriefs 2001 619 s sf: Su Signature Analysis • Simulated Annealing • Sine Anno • s: Distance. Path • Path Length • Laplace Variable • Single Access. Single Aircraft. Single Aisle. Site Activa­ Length of Arc. Long-Range Order Parameter. Response tion. Situational Awareness. Sky Atlas. Small Array. Curve • Saint • Satisfactory • Save • School • Scientific Sobolev Approximation • Sociedad Anonima • Sociedade Anonima • Societa Anonima • Societe Anonyme • So­ • Sculpsit • Sea. Second • Secondary • Section • Sed­ imentation Coefficient • Segundo • See • Semi • Sensi­ lar Activity • Solar Array • Source Acquisition • South tivity Curve • Series • Set • Shilling • Siecle • Siege • Africa • South African • South America • South Amer­ Siehe • Siglo • Sign • Signature • Signed • Silver • Sin ican • South Atlantic • South Australia • South Aus­ • Sine. Singlet • Singular • Sinister. Sinistra • Sister tralian • Spacecraft Adapter • Special Agent • Spectral • Small • Snow • Society • Soft • Solidus • Solo • Son Albedo • Spectrograph Assembly • Spectrum Analysis • • Southerly • Specific Entropy • Spectral Transmission Spectrum Analyzer • Spin Axis • Splitting Amplifier • • Spherical. Spin Quantum Number. Steamer. Steel Station Address. Station Automatique • Storage Alter­ • Stem. Stere • Stock. Stoichiometric Oxidant-to-Fuel ation • Storage Area • Store Address • Strongly Agree • Ratio • Strange • Stratus • Strong Absorption • Su • Structural Analyzer • Structured Analysis • Su Alteza • Siidlich • Sun • Sunny • sur • Sustantivo • Symmetrical Subaccount.