T. S. Kim and S. H. Jeong Korea Atomic Energy Research Institute, Daejeon, Korea

Size: px
Start display at page:

Download "T. S. Kim and S. H. Jeong Korea Atomic Energy Research Institute, Daejeon, Korea"

Transcription

1 KJ workshop 2016 Korea B. Na, J. H. Jeong, S. W. Jung, S. J. Wang, J. G. Kwak, Y. S. Kim, and NBI Team National Fusion Research Institute, Daejeon, Korea T. S. Kim and S. H. Jeong Korea Atomic Energy Research Institute, Daejeon, Korea 1

2 NBI-1 has been major heating source for KSTAR operation 1 beam box with three ion sources 100 kev, D+ based arc discharge/ion sources placed in horizontal mid-plane On-axis CD profile No. 2 (2012) No. 1 (2010) No. 3 (2014) Long pulse capable positive ion based ion source & multi-aperture plasma grid with CuCrZr SECOND Beam Line 2

3 KSTAR for high Beta & steady-state operation Main mission of KSTAR is to achieve Advanced Tokamak (AT) operation mode in long pulse capable superconducting tokamak device High β & Steady-state operation (fully non-inductive CD) Basically target to high betan, steady-state Increased power and off-axis current drive Approach to high betat & low q95 For broad q profile with larger I P operation Approach to high betap & q95 Stable operation with high B T operation (2016) 3

4 Off-axis CD for advanced tokamak mode One approach to AT mode is utilizing bootstrap current. Additional off-axis CD provides more flexible, localized control of current profile. Current profile is controlled by the angle between NBI and magnetic field pitch angle. M. Murakami et al., NF 49, (2009). 4

5 New tangential NBI having off-axis CD capability tangential radius Advantages maximizing driving current maximizing/optimizing off-axis CD capability compromise with installation constraints minimizing additional R&D requirements Specification of NBI2 vertical slant angle Beam energy <100 kev Beam power <6 MW Duration <300 sec Tangential radius 1.6m Vertical slant angle 0, +/

6 Vertical slant angle determines off-axis capability vertical slant angle scan for up-looking beam At lower angle, optimum R t moves to higher radius At higher angle, off-axis characteristics are enhanced, however efficiency decreases Angle 7.5 degrees seems to be better for CD, however absorption decreases At lower angle (5.5 deg), absorption increases Engineering limit ~ 5.5 deg. I drv rho peak P abs /P b rho w 6

7 Accident on ion dump in 2016 campaign Surface metal of full energy ion dump melted. Even though TC array is installed, the failure was not alarmed. Sudden change of surface metal may not be detected.

8 Heat load calculation using BTR code <NBI-2 specifications> Specifications Remarks Beam energy 100 kev Injected neutral beam power >6 MW = 2.0 MW 3 ea Number of Ion sources 3 EA Beam target position, (R t ) 1.6 m The goal of the BTR calculation - Neutral beam transport, loss and ionization calculation - Heat load calculation of beam line components by collision of neutron or ion particles BTR code calculation results without beamline components Vertical slant angle 5.5 Beam size Beam input port 450 mm 130 mm H port < Size of ion source for the NBI-2 > 130mm 450 mm ( No. of beamlets: ) Beam energy 100 kev Beam current 60 A No. of Beamlets No. of Focal beamlets 8 3 Focal position(m) 10 Beam power@12m(in Tokamak)(MW) 5.5 Transmission rate(%)

9 BTR calculation with beam line components-ii single beam three beams <Full energy> Full energy <Full energy> <Half energy> <1/3 energy> Total loaded beam power(mw) Peak power density(mw/m 2 ) Full energy Half energy 1/3 energy Total loaded beam power(mw) Peak power density(mw/m 2 ) The cooling capacity of hypervapotron is satisfied ( <10MW/m 2 ). The margin is not enough Heat load on a calorimeter: MW/m2

10 Improvement of ion dump-i IR camera will be installed to monitor front surface temperature in real-time Camera with alarm system partially replaces TC arrays at the back of target Two cameras will see both full and half energy dump for feasibility study (harsh environment unstable temperature, electric noise, neutron, magnetic field)

11 Improvement of ion dump-ii 0kV 0kV H + Ion dump 0kV H + H + Neutralizer H Plasma Ion beam trajectory not inducing depression electric potential Acceleration grid Bending magnet 50kV 0kV Energy recovery ion dump is being studied Reducing thermal load Increasing power efficiency 50kV Ion beam trajectory inducing depression electric potential

12 Improvement of full energy beam fraction E=0 IS-B 90kV n n H H = C 21 I α, E / 2 I F α, E A * l l, E l C 21 = * l Fl, E / 2 Al λ third 0 = λ 0 half v c cosθ full Preparing a full energy fraction measurement system. Doppler shift of D-alpha * S. J. Yoo et al., RSI 71, 1421 (2000). 24

13 Summary Main mission of KSTAR is steady state high beta AT mode operation. Off-axis CD provides AT operation and more controllability of current profile. The effect of slant angle on heating and CD is calculated, but 5.5 degree is determined by engineering limit. Heat loads on beam components satisfy the heat capability of hypervapotron. Ion dump temperature measurement system is under consideration. Ion energy recovery system and full energy beam fraction are being studied. 13

14 Thank you for your attention! Inquiry/feedback: 14

Plan of Off-axis Neutral Beam Injector in KSTAR

Plan of Off-axis Neutral Beam Injector in KSTAR KSTAR conference, Feb 25-27, 2015, Daejeon (DCC), Korea Plan of Off-axis Neutral Beam Injector in KSTAR Feb. 26, 2015 DCC, Daejeon, Korea Young-soon Bae a L. Terzolo a, K.S. Lee a, H.K. Kim a, H.L. Yang

More information

Development of Long Pulse Neutral Beam Injector on JT-60U for JT-60SA

Development of Long Pulse Neutral Beam Injector on JT-60U for JT-60SA Development of Long Pulse Neutral Beam Injector on JT-60U for JT-60SA M.Hanada, Y.Ikeda, L. Grisham 1, S. Kobayashi 2, and NBI Gr. Japan Atomic Energy Agency, 801-1 Mukohyama, Naka, Ibaraki-ken, 311-0193,

More information

Development of a Systematic, Self-consistent Algorithm for the K-DEMO Steady-state Operation Scenario

Development of a Systematic, Self-consistent Algorithm for the K-DEMO Steady-state Operation Scenario Development of a Systematic, Self-consistent Algorithm for the K-DEMO Steady-state Operation Scenario J.S. Kang 1, J.M. Park 2, L. Jung 3, S.K. Kim 1, J. Wang 1, D. H. Na 1, C.-S. Byun 1, Y. S. Na 1, and

More information

Beam Species Characteristics of High Current Ion Source for EAST Neutral Beam Injector

Beam Species Characteristics of High Current Ion Source for EAST Neutral Beam Injector Applied Physics Research; Vol. 8, No. 3; 2016 ISSN 1916-9639 E-ISSN 1916-9647 Published by Canadian Center of Science and Education Beam Species Characteristics of High Current Ion Source for EAST Neutral

More information

Fusion Development Facility (FDF) Mission and Concept

Fusion Development Facility (FDF) Mission and Concept Fusion Development Facility (FDF) Mission and Concept Presented by R.D. Stambaugh PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION University of California Los Angeles FNST Workshop

More information

Beyond ITER: Neutral beams for DEMO

Beyond ITER: Neutral beams for DEMO Beyond ITER: Neutral beams for DEMO Roy McAdams Plasma Heating Unit Tokamak and Neutral Beam Operations ICIS 2013, Chiba, Japan 10 th September 2013 CCFE is the fusion research arm of the United Kingdom

More information

IT/P7-4 High energy, high current accelerator development for ITER NBI at JADA

IT/P7-4 High energy, high current accelerator development for ITER NBI at JADA 1 High energy, high current accelerator development for ITER NBI at JADA M. Kashiwagi 1), M. Taniguchi 1), M. Dairaku 1), H. P. L. de Esch 2), L. R. Grisham 3), L. Svensson 2), H. Tobari 1), N. Umeda 1),

More information

Long pulse and high power density H - ion beam accelerations for ITER - Achievement for 60 s acceleration of 1 MeV beam in QST-

Long pulse and high power density H - ion beam accelerations for ITER - Achievement for 60 s acceleration of 1 MeV beam in QST- NIBS2016 12-16 September 2016 St. Ann s College, Oxford, UK Long pulse and high power density H - ion beam accelerations for ITER - Achievement for 60 s acceleration of 1 MeV beam in QST- N.Umeda, J. Hiratsuka,

More information

Spherical Torus Fusion Contributions and Game-Changing Issues

Spherical Torus Fusion Contributions and Game-Changing Issues Spherical Torus Fusion Contributions and Game-Changing Issues Spherical Torus (ST) research contributes to advancing fusion, and leverages on several game-changing issues 1) What is ST? 2) How does research

More information

Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device

Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device REVIEW OF SCIENTIFIC INSTRUMENTS 76, 053505 2005 Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device K. Ida, a

More information

First plasma operation of Wendelstein 7-X

First plasma operation of Wendelstein 7-X First plasma operation of Wendelstein 7-X R. C. Wolf on behalf of the W7-X Team *) robert.wolf@ipp.mpg.de *) see author list Bosch et al. Nucl. Fusion 53 (2013) 126001 The optimized stellarator Wendelstein

More information

MITICA: il prototipo dell'iniettore di neutri da 1 MeV-22 MW per ITER

MITICA: il prototipo dell'iniettore di neutri da 1 MeV-22 MW per ITER MITICA: il prototipo dell'iniettore di neutri da 1 MeV-22 MW per ITER P.Sonato 1/29 Acronimi & partners PRIMA Padova Research on Injector Megavolt Accelerated Saranno ospitati due esperimenti SPIDER Source

More information

Overview of Pilot Plant Studies

Overview of Pilot Plant Studies Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology

More information

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Kenichi NAGAOKA, Masayuki YOKOYAMA, Yasuhiko TAKEIRI, Katsumi IDA, Mikiro YOSHINUMA, Seikichi MATSUOKA 1),

More information

Fast ion physics in the C-2U advanced, beam-driven FRC

Fast ion physics in the C-2U advanced, beam-driven FRC Fast ion physics in the C-2U advanced, beam-driven FRC Richard Magee for the TAE Team 216 US-Japan Workshop on the Compact Torus August 23, 216! High β FRC embedded in magnetic mirror is a unique fast

More information

Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD

Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD 21st IAEA Fusion Energy Conference Chengdu, China, 16-21 October, 2006 IAEA-CN-149/ Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD K. Saito et al. NIFS-851 Oct.

More information

Effect of Magnetic Shear on Propagation and Absorption of EC Waves

Effect of Magnetic Shear on Propagation and Absorption of EC Waves Japan-Korea Workshop on Heating and Current Drive KSTAR Conference, Daejeon Convention Center, Feb. 5-7, 015 Effect of Magnetic Shear on Propagation and Absorption of EC Waves Presented by K. Nagasaki

More information

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory

Localized Electron Cyclotron Current Drive in DIII D: Experiment and Theory Localized Electron Cyclotron Current Drive in : Experiment and Theory by Y.R. Lin-Liu for C.C. Petty, T.C. Luce, R.W. Harvey,* L.L. Lao, P.A. Politzer, J. Lohr, M.A. Makowski, H.E. St John, A.D. Turnbull,

More information

Long-pulse acceleration of 1MeV negative ion beams toward ITER and JT-60SA neutral beam injectors

Long-pulse acceleration of 1MeV negative ion beams toward ITER and JT-60SA neutral beam injectors 1 FIP/1-3Ra Long-pulse acceleration of 1MeV negative ion beams toward ITER and JT-60SA neutral beam injectors J. Hiratsuka 1, A. Kojima 1, N. Umeda 1, M. Hanada 1, M. Kashiwagi 1, M. Yoshida 1, R. Nishikiori

More information

THE OPTIMAL TOKAMAK CONFIGURATION NEXT-STEP IMPLICATIONS

THE OPTIMAL TOKAMAK CONFIGURATION NEXT-STEP IMPLICATIONS THE OPTIMAL TOKAMAK CONFIGURATION NEXT-STEP IMPLICATIONS by R.D. STAMBAUGH Presented at the Burning Plasma Workshop San Diego, California *Most calculations reported herein were done by Y-R. Lin-Liu. Work

More information

PFC/JA NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT

PFC/JA NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT PFC/JA-88-12 NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT J. Wei, L. Bromberg, R. C. Myer, and D. R. Cohn Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts 2139 To

More information

Progress in long pulse production of powerful negative ion beams for JT-60SA and ITER

Progress in long pulse production of powerful negative ion beams for JT-60SA and ITER 1 FIP/2-5Rb Progress in long pulse production of powerful negative ion beams for JT-60SA and ITER A. Kojima 1), N. Umeda 1), M. Hanada 1), M. Yoshida 1), M. Kashiwagi 1), H. Tobari 1), K. Watanabe 1),

More information

Neutral beam plasma heating

Neutral beam plasma heating Seminar I b 1 st year, 2 nd cycle program Neutral beam plasma heating Author: Gabrijela Ikovic Advisor: prof.dr. Tomaž Gyergyek Ljubljana, May 2014 Abstract For plasma to be ignited, external heating is

More information

Toward the Realization of Fusion Energy

Toward the Realization of Fusion Energy Toward the Realization of Fusion Energy Nuclear fusion is the energy source of the sun and stars, in which light atomic nuclei fuse together, releasing a large amount of energy. Fusion power can be generated

More information

ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER

ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER D. BOUCHER 1, D. MOREAU 2, G. VAYAKIS 1, I. VOITSEKHOVITCH 3, J.M. ANÉ 2, X. GARBET 2, V. GRANDGIRARD 2, X. LITAUDON 2, B. LLOYD

More information

Diagnostics for Burning Plasma Physics Studies: A Status Report.

Diagnostics for Burning Plasma Physics Studies: A Status Report. Diagnostics for Burning Plasma Physics Studies: A Status Report. Kenneth M. Young Princeton Plasma Physics Laboratory UFA Workshop on Burning Plasma Science December 11-13 Austin, TX Aspects of Plasma

More information

Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD )

Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD ) Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD ) Masayuki HOMMA, Sadayoshi MURAKAMI, Hideo NUGA and Hiroyuki YAMAGUCHI Department of Nuclear Engineering, Kyoto

More information

Physics of fusion power. Lecture 14: Anomalous transport / ITER

Physics of fusion power. Lecture 14: Anomalous transport / ITER Physics of fusion power Lecture 14: Anomalous transport / ITER Thursday.. Guest lecturer and international celebrity Dr. D. Gericke will give an overview of inertial confinement fusion.. Instabilities

More information

HT-7U* Superconducting Tokamak: Physics design, engineering progress and. schedule

HT-7U* Superconducting Tokamak: Physics design, engineering progress and. schedule 1 FT/P2-03 HT-7U* Superconducting Tokamak: Physics design, engineering progress and schedule Y.X. Wan 1), P.D. Weng 1), J.G. Li 1), Q.Q. Yu 1), D.M. Gao 1), HT-7U Team 1) Institute of Plasma Physics, Chinese

More information

Thermographic measurements of power loads to plasma facing components at Wendelstein 7-X

Thermographic measurements of power loads to plasma facing components at Wendelstein 7-X Thermographic measurements of power loads to plasma facing components at Wendelstein 7-X M.W. Jakubowski 1, A. Ali 1, P. Drewelow 1, H. Niemann 1, F. Pisano 4, A. Puig Sitjes 1, G. Wurden 3, C. Biedermann

More information

Integrated Transport Modeling of High-Field Tokamak Burning Plasma Devices

Integrated Transport Modeling of High-Field Tokamak Burning Plasma Devices Integrated Transport Modeling of High-Field Tokamak Burning Plasma Devices Arnold H. Kritz, T.Onjun,C.Nguyen,P.Zhu,G.Bateman Lehigh University Physics Department 16 Memorial Drive East, Bethlehem, PA 1815

More information

Influence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator

Influence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator EX/P- Influence of ECR Heating on NBI-driven Alfvén Eigenmodes in the TJ-II Stellarator Á. Cappa, F. Castejón, T. Estrada, J.M. Fontdecaba, M. Liniers and E. Ascasíbar Laboratorio Nacional de Fusión CIEMAT,

More information

Energetic Ion Confinement and Lost Ion Distribution in Heliotrons

Energetic Ion Confinement and Lost Ion Distribution in Heliotrons Energetic Ion Confinement and Lost Ion Distribution in Heliotrons S. Murakami, Y. Masaoka, T. Yamamot, A. Fukuyama, M. Osakabe1), K. Ida1), M. Yoshinuma1) T. Ozaki1), T. Tokuzawa1), M. Isobe1), M. Nishiura1),

More information

and expectations for the future

and expectations for the future 39 th Annual Meeting of the FPA 2018 First operation of the Wendelstein 7-X stellarator and expectations for the future Hans-Stephan Bosch Max-Planck-Institut für Plasmaphysik Greifswald, Germany on behalf

More information

ITER Participation and Possible Fusion Energy Development Path of Korea

ITER Participation and Possible Fusion Energy Development Path of Korea 1 ITER Participation and Possible Fusion Energy Development Path of Korea C. S. Kim, S. Cho, D. I. Choi ITER Korea TFT, 52 Eoeun-dong, Yuseong-gu, Daejeon 305-333, Korea kimkim@kbsi.re.kr The objective

More information

A Faster Way to Fusion

A Faster Way to Fusion A Faster Way to Fusion 2017 Tokamak Energy Tokamak Energy Ltd Company Overview April 2018 Our Mission To deliver to mankind a cheap, safe, secure and practically limitless source of clean energy fusion

More information

Physics-based Investigation of Negative Ion Behavior in a Negativeion-rich Plasma using Integrated Diagnostics

Physics-based Investigation of Negative Ion Behavior in a Negativeion-rich Plasma using Integrated Diagnostics Physics-based Investigation of Negative Ion Behavior in a Negativeion-rich Plasma using Integrated Diagnostics K. Tsumori 1,2, Y. Takeiri 1,2, K. Ikeda 1, H. Nakano 1,2, S. Geng 2, M. Kisaki 1, M. Wada

More information

Response of thin foil Faraday Cup lost alpha particle detector in intense neutron and gamma ray radiation fields

Response of thin foil Faraday Cup lost alpha particle detector in intense neutron and gamma ray radiation fields Response of thin foil Faraday Cup lost alpha particle detector in intense neutron and gamma ray radiation fields F.E. Cecil 1, V. Kiptily 2, D. Darrow 3, A. Horton 2, K. Fullard 2, K. Lawson 2, G. Matthews

More information

Reconstruction of the two-dimensional energy flux profile of a particle beam using thermographic measurements

Reconstruction of the two-dimensional energy flux profile of a particle beam using thermographic measurements Università degli Studi di Padova Dipartimento di Ingegneria Industriale Corso di Laurea Magistrale in Ingegneria Energetica Reconstruction of the two-dimensional energy flux profile of a particle beam

More information

Physical Performance Analysis And The Progress Of The Development Of The Negative Ion RF Source For The ITER NBI System

Physical Performance Analysis And The Progress Of The Development Of The Negative Ion RF Source For The ITER NBI System Physical Performance Analysis And The Progress Of The Development Of The Negative Ion RF Source For The ITER NBI System U. Fantz, P. Franzen, W. Kraus, M. Berger, S. Christ-Koch, H. Falter, M. Fröschle,

More information

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak 1 EXS/P2-19 Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak T. Yamada 1), R. Imazawa 2), S. Kamio 1), R. Hihara 1), K. Abe 1), M. Sakumura 1), Q. H. Cao 1), H. Sakakita

More information

N NBI DEVELOPMENT STATUS IN KURCHATOV INSTITUTE

N NBI DEVELOPMENT STATUS IN KURCHATOV INSTITUTE Russian Research Centre KURCHATOV INSTITUTE Institute of Nuclear Fusion N NBI DEVELOPMENT STATUS IN KURCHATOV INSTITUTE Presented by V.M. Kulygin Injectors, Padova, ITALY, 9 11 May, 2005 Negative Ion Based

More information

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges by J.R. Ferron with T.C. Luce, P.A. Politzer, R. Jayakumar, * and M.R. Wade *Lawrence Livermore

More information

Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan

Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan The Sun Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan 2017 CNS Conference Niagara Falls, June 4-7, 2017 Tokamak Outline Fusion

More information

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li Axisymmetric Tandem Mirrors: Stabilization and Confinement Studies R. F. Post, T. K. Fowler*, R. Bulmer, J. Byers, D. Hua, L. Tung Lawrence Livermore National Laboratory *Consultant, Presenter This talk

More information

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory The Path to Fusion Energy creating a star on earth S. Prager Princeton Plasma Physics Laboratory The need for fusion energy is strong and enduring Carbon production (Gton) And the need is time urgent Goal

More information

PoS(ECPD2015)109. Planned Active Spectroscopy in the Neutral Beam Injectors of W7-X

PoS(ECPD2015)109. Planned Active Spectroscopy in the Neutral Beam Injectors of W7-X Planned Active Spectroscopy in the Neutral Beam Injectors of W7-X Juergen Baldzuhn 1, Oliver Ford, Paul McNeely, Torsten Richert, W7-X Team Max-Planck Institut fuer Plasmaphysik, EURATOM Assoc., 17491

More information

A Multi-beamlet Injector for Heavy Ion Fusion: Experiments and Modeling

A Multi-beamlet Injector for Heavy Ion Fusion: Experiments and Modeling A Multi-beamlet Injector for Heavy Ion Fusion: Experiments and Modeling G.A. Westenskow, D.P. Grote; LLNL J.W. Kwan, F. Bieniosek; LBNL PAC07 - FRYAB01 Albuquerque, New Mexico June 29, 2007 This work has

More information

Heating and Current Drive by Electron Cyclotron Waves in JT-60U

Heating and Current Drive by Electron Cyclotron Waves in JT-60U EX/W- Heating and Current Drive by Electron Cyclotron Waves in JT-6U T. Suzuki ), S. Ide ), C. C. Petty ), Y. Ikeda ), K. Kajiwara ), A. Isayama ), K. Hamamatsu ), O. Naito ), M. Seki ), S. Moriyama )

More information

Status and Programmes on Negative Ion Beams at JAERI

Status and Programmes on Negative Ion Beams at JAERI Status and Programmes on Negative Ion Beams at JAERI JAERI Naka Fourth IAEA Technical Meeting on "Negative Ion Based Neutral Beam Injectors Padova, Italia May 9-11, 2005 Summary: Progress at JAERI 2/21

More information

Diamond Neutral Particle Spectrometer at JET and proposal for ITER

Diamond Neutral Particle Spectrometer at JET and proposal for ITER Diamond Neutral Particle Spectrometer at JET and proposal for ITER Krasilnikov V.A. (vkrasilnikov@triniti.ru) SRC RF TRINITI, Troitsk, Moscow, Russia A compact fast corpuscular spectrometer with a detector

More information

Modelling of JT-60U Detached Divertor Plasma using SONIC code

Modelling of JT-60U Detached Divertor Plasma using SONIC code J. Plasma Fusion Res. SERIES, Vol. 9 (2010) Modelling of JT-60U Detached Divertor Plasma using SONIC code Kazuo HOSHINO, Katsuhiro SHIMIZU, Tomonori TAKIZUKA, Nobuyuki ASAKURA and Tomohide NAKANO Japan

More information

Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads

Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads Mitglied der Helmholtz-Gemeinschaft Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads J. Linke, J. Du, N. Lemahieu, Th. Loewenhoff, G. Pintsuk, B. Spilker, T. Weber,

More information

Beam Driven Alfvén Eigenmodes and Fast Ion Transport in the DIII-D and ASDEX Upgrade (AUG) Tokamaks

Beam Driven Alfvén Eigenmodes and Fast Ion Transport in the DIII-D and ASDEX Upgrade (AUG) Tokamaks Beam Driven Alfvén Eigenmodes and Fast Ion Transport in the DIII-D and ASDEX Upgrade (AUG) Tokamaks by M.A. Van Zeeland 1 M. García-Muñoz 2, W.W. Heidbrink 3, I. Classen 4, R.K. Fisher 1, B. Geiger 2,

More information

The fast-ion distribution function

The fast-ion distribution function The fast-ion distribution function Source Collisions Orbits RF Losses W. Heidbrink 3 MeV & 14.7 MeV protons Charge Exchange Reactivity σv Complex neutral beam sources are described by a few parameters

More information

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets

Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets PFC/JA-91-5 Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets E. A. Chaniotakis L. Bromberg D. R. Cohn April 25, 1991 Plasma Fusion Center Massachusetts Institute of Technology

More information

Modeling activities on the negative-ion-based Neutral Beam Injectors of the Large Helical Device

Modeling activities on the negative-ion-based Neutral Beam Injectors of the Large Helical Device Modeling activities on the negative-ion-based Neutral Beam Injectors of the Large Helical Device P. Agostinetti a, V. Antoni a, M. Cavenago b, G. Chitarin a, H. Nakano c, N. Pilan a, G. Serianni a, P.

More information

The New Sorgentina Fusion Source Project

The New Sorgentina Fusion Source Project The New Sorgentina Fusion Source Project P. Agostini, P. Console Camprini, D. Bernardi, M. Pillon, M. Frisoni, M. Angelone, A. Pietropaolo, P. Batistoni, A. Pizzuto ENEA Agenzia Nazionale per le Nuove

More information

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,

More information

Innovative fabrication method of superconducting magnets using high T c superconductors with joints

Innovative fabrication method of superconducting magnets using high T c superconductors with joints Innovative fabrication method of superconducting magnets using high T c superconductors with joints (for huge and/or complicated coils) Nagato YANAGI LHD & FFHR Group National Institute for Fusion Science,

More information

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation P.T. Bonoli, A. E. Hubbard, J. Ko, R. Parker, A.E. Schmidt, G. Wallace, J. C. Wright, and the Alcator C-Mod

More information

Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk

Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk Max-Planck-Institut für Plasmaphysik Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk Robert Wolf robert.wolf@ipp.mpg.de www.ipp.mpg.de Contents Magnetic confinement The stellarator

More information

Conceptual design of an energy recovering divertor

Conceptual design of an energy recovering divertor Conceptual design of an energy recovering divertor Derek Baver Lodestar Research Corporation Conceptual design of an energy recovering divertor, D. A. Baver, Lodestar Research Corporation. Managing divertor

More information

Technological and Engineering Challenges of Fusion

Technological and Engineering Challenges of Fusion Technological and Engineering Challenges of Fusion David Maisonnier and Jim Hayward EFDA CSU Garching (david.maisonnier@tech.efda.org) 2nd IAEA TM on First Generation of FPP PPCS-KN1 1 Outline The European

More information

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES J. Mandrekas, W.M. Stacey Georgia Institute of Technology M. Murakami, M.R. Wade ORNL G. L. Jackson General Atomics Presented at the

More information

Active Spectroscopy. Neutral Beam Diagnostics for Alcator C-Mod

Active Spectroscopy. Neutral Beam Diagnostics for Alcator C-Mod Active Spectroscopy Neutral Beam Diagnostics for Alcator C-Mod Contents Introduction The diagnostic neutral beam Description Neutral Beam Penetration Diagnostics Profiles Turbulence Conclusions p 13.1

More information

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant

More information

Plasma and Fusion Research: Regular Articles Volume 10, (2015)

Plasma and Fusion Research: Regular Articles Volume 10, (2015) Possibility of Quasi-Steady-State Operation of Low-Temperature LHD-Type Deuterium-Deuterium (DD) Reactor Using Impurity Hole Phenomena DD Reactor Controlled by Solid Boron Pellets ) Tsuguhiro WATANABE

More information

Modelling and Analysis of the JET EP2 Neutral Beam Full Energy Ion Dump Curved End Plate

Modelling and Analysis of the JET EP2 Neutral Beam Full Energy Ion Dump Curved End Plate Contract for the Operation of the JET Facilities Co-Funded by Euratom NJOC-CP(16) 15392 A Shepherd et al. Modelling and Analysis of the JET EP2 Neutral Beam Full Energy Ion Dump Curved End Plate Preprint

More information

GA A26686 FAST ION EFFECTS DURING TEST BLANKET MODULE SIMULATION EXPERIMENTS IN DIII-D

GA A26686 FAST ION EFFECTS DURING TEST BLANKET MODULE SIMULATION EXPERIMENTS IN DIII-D GA A26686 FAST ION EFFECTS DURING TEST BLANKET MODULE SIMULATION EXPERIMENTS IN DIII-D by G.J. KRAMER, B.V. BUDNY, R. ELLIS, W.W. HEIDBRINK, T. KURKI-SUONIO, R. NAZIKIAN, A. SALMI, M.J. SCHAFFER, K. SHINOHARA,

More information

Progress Toward High Performance Steady-State Operation in DIII D

Progress Toward High Performance Steady-State Operation in DIII D Progress Toward High Performance Steady-State Operation in DIII D by C.M. Greenfield 1 for M. Murakami, 2 A.M. Garofalo, 3 J.R. Ferron, 1 T.C. Luce, 1 M.R. Wade, 1 E.J. Doyle, 4 T.A. Casper, 5 R.J. Jayakumar,

More information

Advanced Tokamak Research in JT-60U and JT-60SA

Advanced Tokamak Research in JT-60U and JT-60SA I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development

More information

Lawrence Berkeley National Laboratory Lawrence Berkeley National Laboratory

Lawrence Berkeley National Laboratory Lawrence Berkeley National Laboratory Lawrence Berkeley National Laboratory Lawrence Berkeley National Laboratory Title High current density beamlets from RF Argon source for heavy ion fusion applications Permalink https://escholarship.org/uc/item/6zh6c50m

More information

Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak

Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak M. Garcia-Munoz M. A. Van Zeeland, S. Sharapov, Ph. Lauber, J. Ayllon, I. Classen, G. Conway, J. Ferreira,

More information

Fusion-Enabled Pluto Orbiter and Lander

Fusion-Enabled Pluto Orbiter and Lander Fusion-Enabled Pluto Orbiter and Lander Presented by: Stephanie Thomas DIRECT FUSION DRIVE Team Members Stephanie Thomas Michael Paluszek Princeton Satellite Systems 6 Market St. Suite 926 Plainsboro,

More information

Mission Elements of the FNSP and FNSF

Mission Elements of the FNSP and FNSF Mission Elements of the FNSP and FNSF by R.D. Stambaugh PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Presented at FNST Workshop August 3, 2010 In Addition to What Will Be Learned

More information

Physical Design of MW-class Steady-state Spherical Tokamak, QUEST

Physical Design of MW-class Steady-state Spherical Tokamak, QUEST Physical Design of MW-class Steady-state Spherical Tokamak, QUEST FT/P3-25 K.Hanada 1), K.N.Sato 1), H.Zushi 1), K.Nakamura 1), M.Sakamoto 1), H.Idei 1), M.Hasegawa 1), Y.Takase 2), O.Mitarai 3), T.Maekawa

More information

Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER )

Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER ) Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER ) Daichi HAMADA, Atsushi OKAMOTO, Takaaki FUJITA, Hideki ARIMOTO, Katsuya SATOU and

More information

1999 RESEARCH SUMMARY

1999 RESEARCH SUMMARY 1999 RESEARCH SUMMARY by S.L. Allen Presented to DIII D Program Advisory Committee Meeting January 2 21, 2 DIII D NATIONAL FUSION FACILITY SAN DIEGO 3 /SLA/wj Overview of Physics Results from the 1999

More information

Evolution of Bootstrap-Sustained Discharge in JT-60U

Evolution of Bootstrap-Sustained Discharge in JT-60U EX1-4 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase, a S. Ide, b Y. Kamada, b H. Kubo, b O. Mitarai, c H. Nuga, a Y. Sakamoto, b T. Suzuki, b H. Takenaga, b and the JT-60 Team a University

More information

Particle-in-Cell Simulation of Power Coupling of the Grill of the KSTAR 5.0-GHz LHCD Launcher

Particle-in-Cell Simulation of Power Coupling of the Grill of the KSTAR 5.0-GHz LHCD Launcher Journal of the Korean Physical Society, Vol. 44, No. 5, May 2004, pp. 1207 1214 Particle-in-Cell Simulation of Power Coupling of the Grill of the KSTAR 5.0-GHz LHCD Launcher Y. S. Bae, M. H. Cho and W.

More information

Experimental evaluation of nonlinear collision effect on the beam slowing-down process

Experimental evaluation of nonlinear collision effect on the beam slowing-down process P-2 Experimental evaluation of nonlinear collision effect on the beam slowing-down process H. Nuga R. Seki,2 S. Kamio M. Osakabe,2 M. Yokoyama,2 M. Isobe,2 K. Ogawa,2 National Institute for Fusion Science,

More information

Extension of High-Beta Plasma Operation to Low Collisional Regime

Extension of High-Beta Plasma Operation to Low Collisional Regime EX/4-4 Extension of High-Beta Plasma Operation to Low Collisional Regime Satoru Sakakibara On behalf of LHD Experiment Group National Institute for Fusion Science SOKENDAI (The Graduate University for

More information

Status of A Positron-Electron Experiment (APEX) towards the formation of pair plasmas

Status of A Positron-Electron Experiment (APEX) towards the formation of pair plasmas Status of A Positron-Electron Experiment (APEX) towards the formation of pair plasmas H. Saitoh 1,5, J. Stanja 1, T. Sunn Pedersen 1,3, U. Hergenhahn 1, E. V. Stenson 1, H. Niemann 1,3, N. Paschkowski

More information

MHD. Jeff Freidberg MIT

MHD. Jeff Freidberg MIT MHD Jeff Freidberg MIT 1 What is MHD MHD stands for magnetohydrodynamics MHD is a simple, self-consistent fluid description of a fusion plasma Its main application involves the macroscopic equilibrium

More information

Resistive Wall Mode Control in DIII-D

Resistive Wall Mode Control in DIII-D Resistive Wall Mode Control in DIII-D by Andrea M. Garofalo 1 for G.L. Jackson 2, R.J. La Haye 2, M. Okabayashi 3, H. Reimerdes 1, E.J. Strait 2, R.J. Groebner 2, Y. In 4, M.J. Lanctot 1, G.A. Navratil

More information

Steady-state operation scenario and the first experimental result on QUEST

Steady-state operation scenario and the first experimental result on QUEST Steady-state operation scenario and the first experimental result on QUEST K.Hanada 1), K.N.Sato 1), H.Zushi 1), K.Nakamura 1), M.Sakamoto 1), H.Idei 1), M.Hasegawa 1), Y.Takase 2), O.Mitarai 3), T.Maekawa

More information

Design window analysis of LHD-type Heliotron DEMO reactors

Design window analysis of LHD-type Heliotron DEMO reactors Design window analysis of LHD-type Heliotron DEMO reactors Fusion System Research Division, Department of Helical Plasma Research, National Institute for Fusion Science Takuya GOTO, Junichi MIYAZAWA, Teruya

More information

1) H-mode in Helical Devices. 2) Construction status and scientific objectives of the Wendelstein 7-X stellarator

1) H-mode in Helical Devices. 2) Construction status and scientific objectives of the Wendelstein 7-X stellarator Max-Planck-Institut für Plasmaphysik 1) H-mode in Helical Devices M. Hirsch 1, T. Akiyama 2, T.Estrada 3, T. Mizuuchi 4, K. Toi 2, C. Hidalgo 3 1 Max-Planck-Institut für Plasmaphysik, EURATOM-Ass., D-17489

More information

Advanced Ion Beam Calorimetry for the Test Facility ELISE

Advanced Ion Beam Calorimetry for the Test Facility ELISE Advanced Ion Beam Calorimetry for the Test Facility ELISE R. Nocentini 1, a), F. Bonomo 2,3, A. Pimazzoni 4, U. Fantz 1, P. Franzen 1, M. Fröschle 1, B. Heinemann 1, R. Pasqualotto 2, R. Riedl 1, B. Ruf

More information

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Derek Sutherland HIT-SI Research Group University of Washington July 25, 2017 D.A. Sutherland -- EPR 2017, Vancouver,

More information

THE DIII D PROGRAM THREE-YEAR PLAN

THE DIII D PROGRAM THREE-YEAR PLAN THE PROGRAM THREE-YEAR PLAN by T.S. Taylor Presented to Program Advisory Committee Meeting January 2 21, 2 3 /TST/wj PURPOSE OF TALK Show that the program plan is appropriate to meet the goals and is well-aligned

More information

Ion Beam Sources for Neutral Beam Injectors: studies and design for components active cooling and caesium ovens

Ion Beam Sources for Neutral Beam Injectors: studies and design for components active cooling and caesium ovens Ion Beam Sources for Neutral Beam Injectors: studies and design for components active cooling and caesium ovens Andrea Rizzolo Consorzio RFX, Padova, Italy andrea.rizzolo@igi.cnr.it Advanced Physics Courses,

More information

Time-dependent Modeling of Sustained Advanced Tokamak Scenarios

Time-dependent Modeling of Sustained Advanced Tokamak Scenarios Time-dependent Modeling of Sustained Advanced Tokamak Scenarios T. A. Casper, L. L. LoDestro and L. D. Pearlstein LLNL M. Murakami ORNL L.L. Lao and H.E. StJohn GA We are modeling time-dependent behavior

More information

Implementation of a long leg X-point target divertor in the ARC fusion pilot plant

Implementation of a long leg X-point target divertor in the ARC fusion pilot plant Implementation of a long leg X-point target divertor in the ARC fusion pilot plant A.Q. Kuang, N.M. Cao, A.J. Creely, C.A. Dennett, J. Hecla, H. Hoffman, M. Major, J. Ruiz Ruiz, R.A. Tinguely, E.A. Tolman

More information

Critical Physics Issues for DEMO

Critical Physics Issues for DEMO Max-Planck-Institut für Plasmaphysik Critical Physics Issues for DEMO L.D. Horton with thanks to the contributors to the EFDA DEMO physics tasks in 2006 and to D.J. Campbell, who organized this effort

More information

Lattice Design and Performance for PEP-X Light Source

Lattice Design and Performance for PEP-X Light Source Lattice Design and Performance for PEP-X Light Source Yuri Nosochkov SLAC National Accelerator Laboratory With contributions by M-H. Wang, Y. Cai, X. Huang, K. Bane 48th ICFA Advanced Beam Dynamics Workshop

More information

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE 1 EX/P6-18 Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE M. Uchida, T. Maekawa, H. Tanaka, F. Watanabe, Y.

More information

LHC operation in 2015 and prospects for the future

LHC operation in 2015 and prospects for the future LHC operation in 2015 and prospects for the future Moriond Workshop La Thuile March 2016 Jörg Wenninger CERN Beams Department Operation group / LHC For the LHC commissioning and operation teams 1 Moriond

More information

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta

KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta 1 THS/P2-05 KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta Y.S. Park 1), S.A. Sabbagh 1), J.W. Berkery 1), J.M. Bialek 1), Y.M. Jeon 2), S.H. Hahn 2), N. Eidietis

More information