Feedback control of the heating power to access the thermally unstable ignition regime in FFHR
|
|
- Gerald Lee
- 5 years ago
- Views:
Transcription
1 Feedback control o the heating power to access the thermally unstable ignition regime in FFHR US-Japan Fusion ower lant Studies and Related Advanced technologies with participation rom China and Korea, Feb.6-8,, Kyoto Univ., Uji, Japan Osamu Mitarai (okai Univ., Kumamoto, Japan) Contents:. Motivation.. Concept or eedback control o unstable regime. Calculated results on ignition access. Disturbance eect on control when coninement and impurity change: 5. Feedback control and diagnostic systems or low temperature and high-density ignition 6. Summary
2 . Motivation: While the eedback control algorithm o the heating power has been developed or the thermally stable ignition regime, preprogramming alone has been used or the thermally unstable ignition regime so ar. his has been one o big issue to be solved in the thermally unstable ignition studies in FFHR. By analogy o the thermally stable regime, new eedback control algorithm is discovered. It works successully during ignition access and is robust to various parameter disturbances. FFHR: Machine parameters R=5.7m a=.5m, = GW, η α =.98 <B>=.5 τ α */τ E =,.5MeV NBI, c =6 GHz, n c =.97 m - [] hermally stable regime: α n =.5, α =., γ ISS95 =.9 [] hermally unstable regime: α n =, α =., γ ISS95 =.
3 . Concept or eedback control o unstable regime:.. Feedback control o ueling (published) Stabilized by ID ueling control " (t) = # e D ( ) + $ t de D ( )% e D ( )dt + d int! & dt ' G o(t) nt the integration time, d the derivative time, [Note: (t)= i (t)< ] he error o the usion power e D ( ) = c(- / o ) [] c=+ or the thermally stable, [] c= - or the thermally unstable, n C B SD decreases - ( - ) < Ignition D SD!"#$%&$& - ( - ) > A Constant o line Stabilization mechanism. Cooling by ueling and heating by reducing ueling. rotates to the CCW. > However, eedback method o the heating power is not discovered yet!!
4 .. Concept or eedback control o heating power: [] In the stable ignition regime, the Sudo density limit restricts the operating point to the high-temperature and low-density regime..5 $ #6 {! DLM n() " n() lim [m # NE [W ] $ }B o [ ] ] =! SUDO! pr a R [m] where ( ) NE = + % # b # s he density limit provides the heating power as! DLM n()[m " (* ] [W ] =! #$ % &,* a R [m] ) pr - +*! SUDO.5 '.* B o [ ] ' 6 " ( / " B " S )
5 Eample o eedback control o the heating power in the thermally stable regime n() (m - ) alpha 5.!/a NE NELM RAIO (d) BEAA 5 ime (s) SSD 5 5 () (kev) <"> (m - /s) n() e (m - ) =.GW <!>=.7 % MW Density Limit at the stable ()(kev) Heating power MW, γ ISS =.9 (γ LHD =.) B=.5, n()~.8 m - < n c, ()~7.8 kev, Γ n ~.5 MW/m, <β>~.9 %, Beam penetration length λ/a~.7 E NBI =.5 MeV 5
6 [] Basic principle o proposed eedback control o the heating power: he thermally stable and unstable operation regime has an inverse relationship with respect to -n ais in OCON. Analogy o the density limit provides the temperature limit. As the density limit restricts the operating point to the low-density regime, the temperature limit restricts it to the low temperature regime. OCON 6
7 @ Artiicially posturated temperature limit: (Similar to the density limit)! () " () = %{ NE [W ] # $6 }B o [ ]( LM lim c ' * &' a R [m] )* Here, c and α C are selected by simulations. his temperature limit is rewritten as * #$ + (! " B " S )% & ' "6 ( ) LM ()-! C a R [m] +., c / B o [ ] Finally, the heating power depends on the measured temperature, and alpha, bremsstrahlung power losses #! " () &) C LM a R [m] $ ' % c ( B o [ ] where γ LM is adjusted to reduce with the time + C * 6 + ( ) + B + S )! LM = () lim () ". () lim = c #{ NE [W ]! "6 }B o [ ]& % ( a R [m] $ % '( ) C ( lim and c are dierent) 7
8 . Calculated results on ignition access: c optimization [-] c = 7.7 kev, α C =. ma =6MW γ ISS =., B=.5, α n =, α =. E=.5MeV annbi n()=8. m -, ()=7. kev, <β>=.5 %, div =.MW/m (9, Δ=. ), (nt = s, di = s) Operating temperature is always lower than the temperature limit. -control n() (m - ) alpha !/a ELM RAIO C(d) FB control NE BEAA SSD 6 8 ime (s) () (kev) <"> (m - /s) n() e (m - ) MW at the unstable emperature limit =.GW <!>=.9 % ()(kev) he operating point passes near the saddle point. 8
9 [-] c = 5.5 kev ma =6MW As the temperature limit is lowered, the heating power or ignition access is increased to pass the higher contour map, and the density also increases leading to worse NBI penetration. -control n() (m - ) alpha !/a ELM RAIO C (d) FB control NE BEAA SSD 6 8 ime (s) () (kev) <"> (m - /s) n() e (m - ) MW at the unstable emperature limit =.GW <!>=.9 % ()(kev) 9
10 [-] c = 8.5 kev ma =6MW As the temperature limit is higher, the operating temperature is increased and the operating point stays longer in the low-density regime avorable or NBI heating. But... -control n() (m - ) alpha!/a ELM RAIO C (d) FB control NE BEAA SSD 6 8 ime (s) () (kev) <"> (m - /s) n() e (m - ) MW at the unstable emperature limit =.GW <!>=.9 % ()(kev)
11 . Disturbance eect when coninement actor or impurity change: [-] Coninement degradation during -5s : γ ISS =..5 (-5s) ( c = 7.7 kev, α C =.) Heating power is increased during coninement degradation phase. n() (m - ) alpha "/a ELM C(d) GHH -control FB control NE RAIO SSD 6 8 ime (s) () (kev).6..8.! ISS (m - /s) n() e (m - ) MW at the unstable =.GW <!>=.9 % ()(kev)
12 [-] Coninement increment during -5s γ ISS =..6 (-5s), B=.5, α n =, α =.E=.5MeV annbi ( c = 7.7 kev, α C =.) Heating power is decreased during coninement improvement phase. n() (m - ) alpha "/a ELM C (d) GHH -control FB control NE RAIO SSD 6 8 ime (s) () (kev).6..8.! ISS (m - /s) n() e (m - ) MW at the unstable =.GW <!>=.9 % ()(kev)
13 [ ] Further c optimization Is c =7.7 kev optimum or wide parameter regime? [--] Lower coninement actor γ ISS =.5 ( c =7.7 kev, di = s) proceeds to the inal one smoothly. -control n() (m - ) alpha !/a ELM RAIO C (d) FB control NE GHH SSD 5 5 ime (s) () (kev) " ISS (m - /s) n() e (m - ) MW 8 6 at the unstable =.GW <!>=.9 % ()(kev)
14 [--] Finite dierential time o di =. s (γ ISS =.5, c =7.7 kev) Oscillations on ueling and heating power appear by inite dierential time in ueling control. stops at the highest temperature on = GW line by introducing the dierential time di. -control n() (m - ) alpha!/a ELM RAIO C (d) FB control NE GHH SSD 5 5 ime (s) () (kev) " ISS (m - /s) n() e (m - ). Final operating point 8 =.GW 6 <!>=.9 % MW ()(kev)
15 [--] Lower temperature limit o c =7. kev (γ ISS =.5, di =. s) When the temperature limit is lowered, operating point proceeds to the inal one smoothly even with the inite dierential time. Lower temperature limit drives the operating point to the low temperature regime at the turning point. n() (m - ) alpha!/a ELM RAIO C(d) -control 5 5 ime (s) FB control NE GHH SSD () (kev) " ISS (m - /s) n() e (m - ) MW 8 6 at the unstable =.GW <!>=.9 % ()(kev) 5
16 [-] Impurity disturbances: I impurity content is increased during heating phase, eedback heating power is increased. Sub-ignition [--] Impurity increment to imp =.5 ( c =7.7 kev, di = s) Sub-Ignition is terminated. -control n() (m - ) alpha !/a ELM RAIO C (d) FB control NE Fimp SSD 5 5 ime (s) () (kev) imp (m - /s) n() e (m - ). 8 6 MW =.GW <!>=.9 % ()(kev) 6
17 [--] Lower temperature limit case ( c =7. kev) (impurity increment to imp =.5, di = s) Sub-ignition is maintained or smaller C. Lower temperature limit can keep the operating point on the contour map in the low temperature regime c =7. kev can be used or wide parameters. -control n() (m - ) alpha !/a ELM RAIO C(d) FB control NE Fimp SSD 5 5 ime (s) () (kev) imp (m - /s) n() e (m - ). 8 6 MW 8 6 at the unstable 8 6 =.GW <!>=.9 % ()(kev) 7
18 [-5] Shutdown phase: [-5-] Heating power eedback in all phases. ( c =7. kev, di = s) Feedback control o the heating power is applied during the shutdown phase. -control n() (m - ) alpha "/a ELM C BEAA (d) FB control NE RAIO SSD 5 5 ime (s) () (kev) ! (m - /s) n() e (m - ) at the unstable MW emperature limit =.GW <!>=.9 % ()(kev) 8
19 [-5-] Heating power is shut o ater s. ( c =7. kev, di = s) n() (m - ) alpha "/a Smooth shutdown has been achieved without the heating power and uelling ELM C BEAA (d) -control FB control NE RAIO SSD 5 5 ime (s) () (kev) ! (m - /s) n() e (m - ) Fusion power is slightly changed rom the set value at the unstable MW emperature limit =.GW <!>=.9 % ()(kev) 9
20 5. Feedback control and diagnostic systems or low temperature and high-density ignition emperature measurement is important or eedback control o heating power during high-density ignition access. R, a, B o HNE n LIMI Feedback Controller! DLC () () Neutron n Detector ( reprogram ( # " (set) " )# " * Eternal Heating (NBI,ICRH,ECRH) Fusion power set value o (t) ( ' ID Contol ( ) Bolometer b e R,B t,v ECE Spectrometer s reprogram Fuel ratio set value {n D /(n D +n )} o ' ( ( Deuterium Fueling System S D ritium Fueling System S Intererometer Diamagnetic loop n D /n measurement n <$> dw/dt L!"#$%&
21 6. Summary [] ID ueling control was already developed or the thermally unstable ignition regime. Analogy o the density limit gives us the hint that postulated temperature limit restricts the operating point to the low-temperature regime. he newly discovered control algorithm or the heating power was successully demonstrated or ignition access to the thermally unstable regime in FFHR. [] Lower c tends to increase the heating power and density, and then reduce the penetration ratio o NBI heating. Higher c tends to stop the operating point i the coninement actor is reduced. [] emperature limit actor o c ~7. kev might be suitable or eedback control or wide parameter regimes. Feedback control method o ueling and heating power has been developed or thermally unstable operation.
The high density ignition in FFHR helical reactor by NBI heating
The high density ignition in FFHR helical reactor by NBI heating Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies with participations of EU and Korea February -, at NIFS in Toki,
More informationHigh-Density, Low Temperature Ignited Operations in FFHR
High-Density, Low Temperature Ignited Operations in FFHR Osamu MITARAI, Akio SAGARA 1), Ryuichi SAKAMOTO 1), Nobuyoshi OHYABU 1), Akio KOMORI 1) and Osamu MOTOJIMA 1) Liberal Arts Education Center, Kumamoto
More informationPlasma 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 informationDesign 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 informationJapan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea (Kyoto University, Uji, Japan, 26-28
Japan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea (Kyoto University, Uji, Japan, 26-28 Feb. 2013) 2/22 FFHR-d1 R c = 15.6 m B c = 4.7 T P fusion
More informationUS-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March at UCSD.
US-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March 5-7 28 at UCSD. Overview Overview of of Design Design Integration Integration toward toward Optimization -type
More informationExhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France
Exhaust scenarios Alberto Loarte Plasma Operation Directorate ITER Organization Route de Vinon sur Verdon, 13067 St Paul lez Durance, France Acknowledgements: Members of ITER Organization (especially R.
More informationHIGH 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 informationD- 3 He HA tokamak device for experiments and power generations
D- He HA tokamak device for experiments and power generations US-Japan Fusion Power Plant Studies Contents University of Tokyo, Japan January -, 5 O.Mitarai (Kyushu Tokai University).Motivation.Formalism,
More informationSTELLARATOR REACTOR OPTIMIZATION AND ASSESSMENT
STELLARATOR REACTOR OPTIMIZATION AND ASSESSMENT J. F. Lyon, ORNL ARIES Meeting October 2-4, 2002 TOPICS Stellarator Reactor Optimization 0-D Spreadsheet Examples 1-D POPCON Examples 1-D Systems Optimization
More information- Plasma Control - Stellarator-Heliotron Control
- Plasma Control - Stellarator-Heliotron Control H.Yamada National Institute for Fusion Science, NINS The University of Tokyo Acknowledgements to T.Akiyama, A.Dinklage, T.Goto, M.Koyabashi, J.Miyazawa,
More informationINTRODUCTION TO MAGNETIC NUCLEAR FUSION
INTRODUCTION TO MAGNETIC NUCLEAR FUSION S.E. Sharapov Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, UK With acknowledgments to B.Alper for use of his transparencies
More information1) 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 informationOverview 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 informationRecent 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 informationA Method of Knock-on Tail Observation Accounting Temperature Fluctuation Using 6 Li+T/D+T Reaction in Deuterium Plasma
A Method of Knock-on Tail Observation Accounting Temperature Fluctuation Using 6 Li+T/D+T Reaction in Deuterium Plasma Yasuko KAWAMOTO and Hideaki MATSUURA Department of Applied Quantum Physics and Nuclear
More informationIgnition Regime and Burn Dynamics of D T-Seeded D 3 He Fuel for Fast Ignition Inertial Confinement Fusion
Ignition Regime and Burn Dynamics of D T-Seeded D 3 He Fuel for Fast Ignition Inertial Confinement Fusion Y. Nakao, K. Tsukida, K. Shinkoda, Y. Saito Department of Applied Quantum Physics and Nuclear Engineering,
More informationEvolution 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 informationStudy on supporting structures of magnets and blankets for a heliotron-type type fusion reactors
JA-US Workshop on Fusion Power Plants and Related Advanced Technologies with participation of EU, Jan. 11-13, 2005, Tokyo, Japan. Study on supporting structures of magnets and blankets for a heliotron-type
More informationDevelopment 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 informationThe 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 informationDesign concept of near term DEMO reactor with high temperature blanket
Design concept of near term DEMO reactor with high temperature blanket Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies March 16-18, 2009 Tokyo Univ. Mai Ichinose, Yasushi Yamamoto
More informationMultifarious Physics Analyses of the Core Plasma Properties in a Helical DEMO Reactor FFHR-d1
1 FTP/P7-34 Multifarious Physics Analyses of the Core Plasma Properties in a Helical DEMO Reactor FFHR-d1 J. Miyazawa 1, M. Yokoyama 1, Y. Suzuki 1, S. Satake 1, R. Seki 1, Y. Masaoka 2, S. Murakami 2,
More informationDIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH
DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK
More informationPhysics & Engineering Physics University of Saskatchewan. Supported by NSERC, CRC
Fusion Energy Chijin Xiao and Akira Hirose Plasma Physics laboratory Physics & Engineering Physics University of Saskatchewan Supported by NSERC, CRC Trends in Nuclear & Medical Technologies April il6-7,
More informationBurn Stabilization of a Tokamak Power Plant with On-Line Estimations of Energy and Particle Confinement Times
Burn Stabilization of a Tokamak Power Plant with On-Line Estimations of Energy and Particle Confinement Times Javier E. Vitela vitela@nucleares.unam.mx Instituto de Ciencias Nucleares Universidad Nacional
More informationFirst 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 informationand 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 informationCritical 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 informationObservation of Alpha Heating in JET DT Plasmas
JET P(98)1 Observation of Alpha Heating in JET DT Plasmas P R Thomas, P Andrew, B Balet, D Bartlett, J Bull, B de Esch, C Gowers, H Guo, G Huysmans, T Jones, M Keilhacker, R König, M Lennholm, P Lomas,
More informationEvolution of Bootstrap-Sustained Discharge in JT-60U
1 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase 1), S. Ide 2), Y. Kamada 2), H. Kubo 2), O. Mitarai 3), H. Nuga 1), Y. Sakamoto 2), T. Suzuki 2), H. Takenaga 2), and the JT-60 Team 1)
More informationEvaluation of Anomalous Fast-Ion Losses in Alcator C-Mod
Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod S. D. Scott Princeton Plasma Physics Laboratory In collaboration with R. Granetz, D. Beals, M. Greenwald MIT PLASMA Science and Fusion Center W.
More informationICF ignition and the Lawson criterion
ICF ignition and the Lawson criterion Riccardo Betti Fusion Science Center Laboratory for Laser Energetics, University of Rochester Seminar Massachusetts Institute of Technology, January 0, 010, Cambridge
More informationHFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION
ASDEX Upgrade Session: "Issues and prospects of effcient fueling for magnetic confinement" HFS ELLET REFUELING FOR HIGH DENSITY TOKAMAK OERATION.T. Lang for the ASDEX Upgrade and JET teams Cubic mm size
More informationINTRODUCTION TO BURNING PLASMA PHYSICS
INTRODUCTION TO BURNING PLASMA PHYSICS Gerald A. Navratil Columbia University American Physical Society - Division of Plasma Physics 2001 Annual Meeting, Long Beach, CA 1 November 2001 THANKS TO MANY PEOPLE
More informationTHE 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 informationDT Fusion Power Production in ELM-free H-modes in JET
JET C(98)69 FG Rimini and e JET Team DT Fusion ower roduction in ELM-free H-modes in JET This document is intended for publication in e open literature. It is made available on e understanding at it may
More informationMHD. 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 informationT. S. Kim and S. H. Jeong Korea Atomic Energy Research Institute, Daejeon, Korea
KJ workshop 2016 W @Pohang, 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
More informationHigh fusion performance at high T i /T e in JET-ILW baseline plasmas with high NBI heating power and low gas puffing
High fusion performance at high T i /T e in JET-ILW baseline plasmas with high NBI heating power and low gas puffing Hyun-Tae Kim, A.C.C. Sips, C. D. Challis, F. Rimini, L. Garzotti, E. Lerche, L. Frassinetti,
More informationInnovative 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 informationControl of the fission chain reaction
Control of the fission chain reaction Introduction to Nuclear Science Simon Fraser University Spring 2011 NUCS 342 April 8, 2011 NUCS 342 (Lecture 30) April 8, 2011 1 / 29 Outline 1 Fission chain reaction
More informationElastic Recoil Detection Method using DT Neutrons for Hydrogen Isotope Analysis in Fusion Materials. Abstract
Elastic Recoil Detection Method using DT Neutrons for Hydrogen Isotope Analysis in Fusion Materials Naoyoshi Kubota, Kentaro Ochiai, Keitaro Kondo 2 and Takeo Nishitani. :Japan Atomic Energy Research Institute,
More informationPHYSICS OF CFETR. Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China.
PHYSICS OF CFETR Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China Dec 4, 2013 Mission of CFETR Complementary with ITER Demonstration of fusion
More informationStudy 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 informationValidation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling
Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling by B.A. Grierson1, C. Chrystal2, W.X. Wang1, J.A. Boedo3, J.S. degrassie2, W.M. Solomon2,
More informationISOTOPE EFFECTS ON CONFINEMENT AND TURBULENCE IN ECRH PLASMA OF LHD
K. TANAKA et al, ISOTOPE EFFECTS ON CONFINEMENT AND TURBULENCE IN ECRH PLASMA OF LHD K. TANAKA National Institute for Fusion Science, National Institutes on Natural Sciences Toki, Japan Email: ktanaka@nifs.ac.jp
More informationStudies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D
Studies of H Mode Plasmas Produced Directly by Pellet Injection in by P. Gohil in collaboration with L.R. Baylor,* K.H. Burrell, T.C. Jernigan,* G.R. McKee, *Oak Ridge National Laboratory University of
More informationProgressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg.
Progressing Performance Tokamak Core Physics Marco Wischmeier Max-Planck-Institut für Plasmaphysik 85748 Garching marco.wischmeier at ipp.mpg.de Joint ICTP-IAEA College on Advanced Plasma Physics, Triest,
More informationFAST 1 : a Physics and Technology Experiment on the Fusion Road Map
Fusion Advanced Studies Torus FAST 1 : a Physics and Technology Experiment on the Fusion Road Map Presented by A. A. Tuccillo on behalf of ENEA-Euratom Association Univ. of Rome Tor Vergata Univ. of Catania
More informationQ, Break-even and the nτ E Diagram for Transient Fusion Plasmas
Q, Break-even and the nτ E Diagram for Transient Plasmas Dale M. Meade Princeton University P.O. Box 451, Princeton, N. J. 08543 Abstract - Q, break-even and the nτe diagram are well defined and understood
More informationThe performance of improved H-modes at ASDEX Upgrade and projection to ITER
EX/1-1 The performance of improved H-modes at ASDEX Upgrade and projection to George Sips MPI für Plasmaphysik, EURATOM-Association, D-85748, Germany G. Tardini 1, C. Forest 2, O. Gruber 1, P. Mc Carthy
More informationASSESSMENT 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 informationIntroduction to Fusion Physics
Introduction to Fusion Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 Energy from nuclear fusion Reduction
More informationEstimations 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 informationStatus of Physics and Configuration Studies of ARIES-CS. T.K. Mau University of California, San Diego
Status of Physics and Configuration Studies of ARIES-CS T.K. Mau University of California, San Diego L.P. Ku, PPPL J.F. Lyon, ORNL P.R. Garabedian, CIMS/NYU US/Japan Workshop on Power Plant Studies and
More informationβ and γ decays, Radiation Therapies and Diagnostic, Fusion and Fission Final Exam Surveys New material Example of β-decay Beta decay Y + e # Y'+e +
β and γ decays, Radiation Therapies and Diagnostic, Fusion and Fission Last Lecture: Radioactivity, Nuclear decay Radiation damage This lecture: nuclear physics in medicine and fusion and fission Final
More informationAspects of Advanced Fuel FRC Fusion Reactors
Aspects of Advanced Fuel FRC Fusion Reactors John F Santarius and Gerald L Kulcinski Fusion Technology Institute Engineering Physics Department CT2016 Irvine, California August 22-24, 2016 santarius@engr.wisc.edu;
More informationSTEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U
Abstract STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-6U A. SAKASAI, H. TAKENAGA, N. HOSOGANE, H. KUBO, S. SAKURAI, N. AKINO, T. FUJITA, S. HIGASHIJIMA, H. TAMAI, N. ASAKURA, K. ITAMI,
More informationHeating 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 informationNotes on fusion reactions and power balance of a thermonuclear plasma!
SA, 3/2017 Chapter 5 Notes on fusion reactions and power balance of a thermonuclear plasma! Stefano Atzeni See S. Atzeni and J. Meyer-ter-Vehn, The Physics of Inertial Fusion, Oxford University Press (2004,
More informationSawtooth mixing of alphas, knock on D, T ions and its influence on NPA spectra in ITER plasma
Sawtooth mixing of alphas, knock on D, T ions and its influence on NPA spectra in ITER plasma F.S. Zaitsev 1, 4, N.N. Gorelenkov 2, M.P. Petrov 3, V.I. Afanasyev 3, M.I. Mironov 3 1 Scientific Research
More informationEffect of rotational transform and magnetic shear on confinement of stellarators
Effect of rotational transform and magnetic shear on confinement of stellarators E. Ascasíbar(1), D. López-Bruna(1), F. Castejón(1), V.I. Vargas(1), V. Tribaldos(1), H. Maassberg(2), C.D. Beidler(2) R.
More informationInvestigation of the 3 He-η system with polarized beams at ANKE
Investigation o the 3 He-η system with olarized beams at ANKE II International Symosium on Mesic Nuclei Setember -5, 013 Institut ür Kernhysik Alons Khoukaz Why η-meson Production Close to Threshold? Do
More informationEnergetic Particle Physics in Tokamak Burning Plasmas
Energetic Particle Physics in Tokamak Burning Plasmas presented by C. Z. (Frank) Cheng in collaboration with N. N. Gorelenkov, G. J. Kramer, R. Nazikian, E. Fredrickson, Princeton Plasma Physics Laboratory
More informationNoninductive 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 informationJoint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics October Introduction to Fusion Leading to ITER
2267-1 Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics 3-14 October 2011 Introduction to Fusion Leading to ITER SNIPES Joseph Allan Directorate for Plasma Operation Plasma Operations
More informationWhere are we with laser fusion?
Where are we with laser fusion? R. Betti Laboratory for Laser Energetics Fusion Science Center Dept. Mechanical Engineering and Physics & Astronomy University of Rochester HEDSA HEDP Summer School August
More informationControl of plasma stored energy for burn control using DIII-D in-vessel coils
Control of plasma stored energy for burn control using DIII-D in-vessel coils The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters. Citation
More informationImpact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor
Impact of High Field & High Confinement on L-mode-Edge Negative Triangularity Tokamak (NTT) Reactor M. Kikuchi, T. Takizuka, S. Medvedev, T. Ando, D. Chen, J.X. Li, M. Austin, O. Sauter, L. Villard, A.
More informationLocal organizer. National Centralized Tokamak
US/Japan Workshop on MHD Stability Control and Related Confinement of Toroidal Plasmas, 6-8 February 2006, JAEA-Naka, Japan with ITPA meeting of MHD Topical Group, 6-9 February Venue and Dates The workshop
More informationTokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011
Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor
More informationDT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift )
DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift ) Tsuguhiro WATANABE National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan (Received
More informationNon-ohmic ignition scenarios in Ignitor
Non-ohmic ignition scenarios in Ignitor Augusta Airoldi IFP, EURATOM-ENEA-CNR Association, Milano, Italy Francesca Bombarda, Giovanna Cenacchi Ignitor Group, ENEA, Italy Bruno Coppi MIT, USA DPP1 APS Meeting
More informationIntegrated radiation monitoring and interlock system for the LHD deuterium experiments
Integrated radiation monitoring and interlock system for the LHD deuterium experiments Nakanishi H. with Safety & Env. Monitoring Team and LHD Information Systems Group National Institute for Fusion Science,
More informationDesign Windows and Economic Aspect of Helical Reactor
Design Windows and Economic Aspect of Helical Reactor Y. Kozaki, S. Imagawa, A. Sagara National Institute for Fusion Science, Toki, Japan Japan-US Workshop, Kashiwa, March 16-18,2009 - Background and Objectives
More informationNeutral 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 informationDevelopment in DIII D Tokamak Hybrid Operation Scenarios
Development in Tokamak Hybrid Operation Scenarios by R.J. Jayakumar in collaboration with M.R. Wade, T.C. Luce, P.A. Politzer, A.W. Hyatt, J.R. Ferron, C.M. Greenfield, E.H. Joffrin, M. Murakami, C.C.
More informationDynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas
Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas K. Ida 1), Y. Sakamoto 2), M. Yoshinuma 1), H. Takenaga 2), K. Nagaoka 1), N. Oyama 2), M. Osakabe 1), M. Yokoyama
More informationAtomic physics in fusion development
Atomic physics in fusion development The next step in fusion development imposes new requirements on atomic physics research by R.K. Janev In establishing the scientific and technological base of fusion
More informationApplication of atomic data to quantitative analysis of tungsten spectra on EAST tokamak
Technical Meeting on Uncertainty Assessment and Benchmark Experiments for Atomic and Molecular Data for Fusion Applications, 19-21 December 2016, Vienna, Austria Application of atomic data to quantitative
More informationAdvanced 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 informationDevelopment of Net-Current Free Heliotron Plasmas in the Large Helical Device
Development of Net-Current Free Heliotron Plasmas in the Large Helical Device A. Komori for the LHD Experimental Group National Institute for Fusion Science Toki, Japan 22nd IAEA Fusion Energy Conference
More informationSuperconducting Magnet Design and R&D with HTS Option for the Helical DEMO Reactor
Superconducting Magnet Design and R&D with HTS Option for the Helical DEMO Reactor N. Yanagi, A. Sagara and FFHR-Team S. Ito 1, H. Hashizume 1 National Institute for Fusion Science 1 Tohoku University
More informationPredicting the Rotation Profile in ITER
Predicting the Rotation Profile in ITER by C. Chrystal1 in collaboration with B. A. Grierson2, S. R. Haskey2, A. C. Sontag3, M. W. Shafer3, F. M. Poli2, and J. S. degrassie1 1General Atomics 2Princeton
More informationMagnetic Confinement Fusion-Status and Challenges
Chalmers energy conference 2012 Magnetic Confinement Fusion-Status and Challenges F. Wagner Max-Planck-Institute for Plasma Physics, Greifswald Germany, EURATOM Association RLPAT St. Petersburg Polytechnic
More informationOPTIMIZATION OF STELLARATOR REACTOR PARAMETERS
OPTIMIZATION OF STELLARATOR REACTOR PARAMETERS J. F. Lyon, L.P. Ku 2, P. Garabedian, L. El-Guebaly 4, L. Bromberg 5, and the ARIES Team Oak Ridge National Laboratory, Oak Ridge, TN, lyonjf@ornl.gov 2 Princeton
More informationFokker-Planck Modelling of NBI deuterons in ITER
Fokker-Planck Modelling of NBI deuterons in ITER V. Yavorskij 1,2), K. Schoepf 1), V. Goloborod ko 1,2), M. Cecconello 3,4), L.G. Eriksson 5), M. Khan 1), V. Kiptily 3), A. Korotkov 3), A. Polevoi 6),
More informationPhysics 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 informationFast Ion Confinement in the MST Reversed Field Pinch
Fast Ion Connement in the MST Reversed Field Pinch Gennady Fiksel B. Hudson, D.J. Den Hartog, R.M. Magee, R. O'Connell, S.C. Prager MST Team - University of Wisconsin - Madison Center for Magnetic Self-Organization
More informationSelf-consistent modeling of ITER with BALDUR integrated predictive modeling code
Self-consistent modeling of ITER with BALDUR integrated predictive modeling code Thawatchai Onjun Sirindhorn International Institute of Technology, Thammasat University, Klong Luang, Pathumthani, 12121,
More informationFast ion generation with novel three-ion radiofrequency heating scenarios:
1 Fast ion generation with novel three-ion radiofrequency heating scenarios: from JET, W7-X and ITER applications to aneutronic fusion studies Yevgen Kazakov 1, D. Van Eester 1, J. Ongena 1, R. Bilato
More informationDer 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 informationIon 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 informationResults From Initial Snowflake Divertor Physics Studies on DIII-D
Results From Initial Snowflake Divertor Physics Studies on DIII-D S. L. Allen, V. A. Soukhanovskii, T.H. Osborne, E. Kolemen, J. Boedo, N. Brooks, M. Fenstermacher, R. Groebner, D. N. Hill, A. Hyatt, C.
More informationIMPURITY 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 informationMachine Learning CS 4900/5900. Lecture 03. Razvan C. Bunescu School of Electrical Engineering and Computer Science
Machine Learning CS 4900/5900 Razvan C. Bunescu School of Electrical Engineering and Computer Science bunescu@ohio.edu Machine Learning is Optimization Parametric ML involves minimizing an objective function
More informationFast 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 informationTHE ADVANCED TOKAMAK DIVERTOR
I Department of Engineering Physics THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and the team 14th PSI QTYUIOP MA D S O N UCLAUCLA UCLA UNIVERSITY OF WISCONSIN THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and
More informationMagnetic 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