Insert Chart, Photo or Image

Slides:



Advertisements
Similar presentations
Control of Magnetic Chaos & Self-Organization John Sarff for MST Group CMSO General Meeting Madison, WI August 4-6, 2004.
Advertisements

Glenn Bateman Lehigh University Physics Department
H-mode characterization for dominant ECR heating and comparison to dominant NBI or ICR heating F. Sommer PhD thesis advisor: Dr. Jörg Stober Academic advisor:
Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
Rotating Wall/ Centrifugal Separation John Bollinger, NIST-Boulder Outline ● Penning-Malmberg trap – radial confinement due to angular momentum ● Methods.
SUGGESTED DIII-D RESEARCH FOCUS ON PEDESTAL/BOUNDARY PHYSICS Bill Stacey Georgia Tech Presented at DIII-D Planning Meeting
Intense Diagnostic Neutral Beam For Burning Plasmas Challenges for ITER and Opportunities for KSTAR Jaeyoung Park Glen Wurden and MFE team Los Alamos National.
The Reversed Field Pinch: on the path to fusion energy S.C. Prager September, 2006 FPA Symposium.
ELECTRON CYCLOTRON SYSTEM FOR KSTAR US-Korea Workshop Opportunities for Expanded Fusion Science and Technology Collaborations with the KSTAR Project Presented.
Introduction to Spherical Tokamak
Runaway Electron Mitigation Collaboration on J-TEXT David Q. Hwang UC Davis Sixth US-PRC Magnetic Fusion Collaboration Workshop Collaborating Institutions:
Systems Analysis for Modular versus Multi-beam HIF Drivers * Wayne Meier – LLNL Grant Logan – LBNL 15th International Symposium on Heavy Ion Inertial Fusion.
Simulations of Neutralized Drift Compression D. R. Welch, D. V. Rose Mission Research Corporation Albuquerque, NM S. S. Yu Lawrence Berkeley National.
OPTIMIZATION OF O 2 ( 1  ) YIELDS IN PULSED RF FLOWING PLASMAS FOR CHEMICAL OXYGEN IODINE LASERS* Natalia Y. Babaeva, Ramesh Arakoni and Mark J. Kushner.
Raman, BPW (W60) 4-5 July 2005 Advanced fueling system for use as a burn control tool Roger Raman University of Washington, Seattle Workshop (W60) on Burning.
Raman,11 STW 3-6 Oct 2005 Fueling Requirements for Steady State Spherical Torus Operation Roger Raman, Thomas R. Jarboe, + Henry W. Kugel University of.
Y. Sakamoto JAEA Japan-US Workshop on Fusion Power Plants and Related Technologies with participations from China and Korea February 26-28, 2013 at Kyoto.
Study of negative ion surface production in caesium-free H 2 plasma PhD student: Kostiantyn Achkasov Tutors: Gilles Cartry and Alain Simonin 3 rd FUSENET.
2011 Damping Rings Lattice Evaluation Mark Palmer Cornell University March 8, 2011.
2D Position Sensitive Detector for Plasma diagnosis
10th ITPA TP Meeting - 24 April A. Scarabosio 1 Spontaneous stationary toroidal rotation in the TCV tokamak A. Scarabosio, A. Bortolon, B. P. Duval,
1 Model of filaments in plasma Nobuhiro Nishino Graduate school of Engineering Hiroshima University 3rd IAEA TM and 11th IWS on ST Place: St.Petersburg.
A New Approach to Fusion Energy
Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
Introduction to Plasma- Surface Interactions Lecture 3 Atomic and Molecular Processes.
Global Stability Issues for a Next Step Burning Plasma Experiment UFA Burning Plasma Workshop Austin, Texas December 11, 2000 S. C. Jardin with input from.
Recent Results of KSTAR
FOM - Institute for Plasma Physics Rijnhuizen Association Euratom-FOM Diagnostics and Control for Burning Plasmas Discussion All of you.
1 13 th ITPA Transport Physics Group Meeting Naka, 1-3 October 2007 V. Mukhovatov ITER Rotation Issues.
JT-60U -1- Access to High  p (advanced inductive) and Reversed Shear (steady state) plasmas in JT-60U S. Ide for the JT-60 Team Japan Atomic Energy Agency.
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority ITB formation and evolution with co- and counter NBI A. R. Field, R. J. Akers,
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
Improved performance in long-pulse ELMy H-mode plasmas with internal transport barrier in JT-60U N. Oyama, A. Isayama, T. Suzuki, Y. Koide, H. Takenaga,
045-05/rs PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Technical Readiness Level For Control of Plasma Power Flux Distribution.
Steady State Discharge Modeling for KSTAR C. Kessel Princeton Plasma Physics Laboratory US-Korea Workshop - KSTAR Collaborations, 5/19-20/2004.
Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.
045-05/rs PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Taming The Physics For Commercial Fusion Power Plants ARIES Team Meeting.
PROPERTIES OF UNIPOLAR DC-PULSED MICROPLASMA ARRAYS AT INTERMEDIATE PRESSURES* Peng Tian a), Chenhui Qu a) and Mark J. Kushner a) a) University of Michigan,
MCZ MCZ NCSX Mission Acquire the physics data needed to assess the attractiveness of compact stellarators; advance understanding.
Accelerators and Sources Report from Discussion Session Jose Alonso 1.
1 V.A. Soukhanovskii/IAEA-FEC/Oct Developing Physics Basis for the Radiative Snowflake Divertor at DIII-D by V.A. Soukhanovskii 1, with S.L. Allen.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
L.R. Baylor 1, N. Commaux 1, T.C. Jernigan 1, S.J. Meitner 1, N. H. Brooks 2, S. K. Combs 1, T.E. Evans 2, M. E. Fenstermacher 3, R. C. Isler 1, C. J.
MAGNETIC CONFINEMENT FUSION Zack Draper | Physics 485 November 23, 2015.
For the NSTX Five-Year Research Program 2009 – 2013 M.G. Bell Facility and Diagnostic Plans.
-200kV -400kV -600kV -800kV -1MV Acceleration of 1 MeV H - ion beams at ITER NB relevant high current density Takashi INOUE, M. Taniguchi, M. Kashiwagi,
Field-Particle Correlation Experiments on DIII-D Frontiers Science Proposal Under weakly collisional conditions, collisionless interactions between electromagnetic.
International Youth Conference on Fusion Energy Conference
Physics of fusion power
Construction and Status of Versatile Experiment Spherical Torus at SNU
Numerical investigation of H-mode threshold power by using LH transition models 8th Meeting of the ITPA Confinement Database & Modeling Topical Group.
Soft and hard mode switching in gyrotrons
Features of Divertor Plasmas in W7-AS
Improvements to the Periodically Oscillating Plasma Sphere Experiment
Generation of Toroidal Rotation by Gas Puffing
J. Menard for the MHD Science Focus Group Tuesday, November 22, 2005
Center for Plasma Edge Simulation
L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European.
R & D Status of Beam Neutralization System M. Sasao, K. Shinto, M
ITERに係わる原子分子過程 Atomic and Molecular Processes in ITER SHIMADA, Michiya ITER International Team Annual Meeting of Japan Society of Plasma Science and Nuclear.
A.D. Turnbull, R. Buttery, M. Choi, L.L Lao, S. Smith, H. St John
Influence of energetic ions on neoclassical tearing modes
The Gas Dynamic Trap (GDT) Neutron Source
N. Oyama, H. Urano, Y. Sakamoto
Mikhail Z. Tokar and Mikhail Koltunov
Stellarator Program Update: Status of NCSX & QPS
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

Insert Chart, Photo or Image Technology to Produce Rotation in Reactor Systems by N.W. Eidietis General Atomics Presented to FESAC TEC Rockville, MD May 31, 2017 Hemsworth New J. Phys. 2017 Insert Chart, Photo or Image Raman Fusion Eng. Design 2008

Fusion reactors will lack the beneficial rotation of contemporary devices Rotation & shear can provide many benefits Improved confinement Avoidance of locked modes, stabilization of tearing modes, RWM, ballooning mode etc… ITER & reactors will rotate slowly due to relatively small neutral beam (NBI) torque Maintaining Q in reactor prioritizes minimizing input power DIII-D  ITER: NBI power increases 2-3X, mass increases > 40X Momentum input efficiency (P/E, or ϵ) falls with increasing beam energy ∝ 𝑚/𝐸 Fusion reactors would benefit greatly from development of efficient toroidal momentum sources Solomon NF 53 2013 Buttery PoP 15 2008

Low energy + high mass key to increasing ϵ Low energy NBI (LNBI) Two technologies show promise for efficiently injecting angular momentum into reactor Low energy + high mass key to increasing ϵ Low energy NBI (LNBI) Ubiquitous technology in fusion Penetration limited by ionization Steady state Compact toroid injection (CTI) Studied on small tokamaks + military Penetrates until kinetic pressure = magnetic pressure (𝜌 𝑉 2 = 𝐵 2 / 𝜇 0 ) Pulsed Hemsworth New J. Phys. 2017 Onchi Fusion Eng. Design 2017

ITER NBI: 33MW, 1 MeV negative ion beam Low energy NBI: Low energy NBI case study: Double ITER injected torque with < 10% reduction in Q ITER NBI: 33MW, 1 MeV negative ion beam Low energy NBI: Power = 3 MW  Momentum injection efficiency 𝜖 𝐿𝑁𝐵𝐼 =10 𝜖 𝐼𝑇𝐸𝑅 Accelerating voltage: 𝑉 𝐿𝑁𝐵𝐼 𝑉 𝐼𝑇𝐸𝑅 = 𝜖 𝐼𝑇𝐸𝑅 𝜖 𝐿𝑁𝐵𝐼 2  V LNBI = 10𝑘𝑉 Current: I LNBI = 3𝑀𝑊 10 𝑘𝑉 =300𝐴 Perveance (𝑰/ 𝑽 𝟑 𝟐 ) is key parameter quantifying space charge limit for electrostatic accelerator ITER NBI: 4𝑥 10 −8 𝐴/ 𝑉 3 2 (negative ion) DIII-D NBI: 3𝑥 10 −6 𝐴/ 𝑉 3 2 (positive ion) LNBI: 3𝑥 10 −4 𝐴/ 𝑉 3 2 (positive ion) Note: Molecular D2 LNBI would increase 𝜖 by 2 Tech Development: 100x perveance increase

Technological developments required for LNBI Hemsworth New J. Phys. 2017 Goal: Increase perveance 100X Method 1: Increase area of ion source & accelerator grid Conceptually simple, but space at premium in toroidal geometry Limited by port size & focusing optics Method 2: Increase beam brightness Minimizes size Requires ion source development (increase A/m2) Increase aperture density in accelerator grid Cooling & beamlet focusing challenging ITER NBI Accelerator grid Cooling channel Aperture

Uncertainties exist in effectiveness of LNBI momentum transfer to plasma Low energy particles will not penetrate beyond reactor pedestal Will momentum efficiently transfer momentum to plasma medge? How significant will LNBI ion losses at edge be? Will edge momentum effectively transport to core region? Pedestal Te LNBI stops here LNBI Plasma minor radius

Mature technology basis exists for LNBI development Large pool of expertise exists for rapid development of high perveance LNBI system Method 1: Increase source & accelerator area Could be brought to TRL5 in 2-3 years without large technical leaps, but subsequent retrofit into existing NBI may prove difficult due to size Method 2: Increase source & accelerator brightness May require longer (5 years) to TRL5, but subsequent retrofit for TRL6 demonstration in existing mid-sized tokamak much easier

ITER Scale CTI Case Study (see Raman FED 2008) Tech Development: CW operation CTI Specifications Power: 5.5 MW Repetition rate: 20 Hz Injection velocity: 500 km/s Injected mass/ kinetic energy per shot: 2.2 mg D2 / 275 kJ Parameters demonstrated, single pulse [Degnan Phys. Fluids B (1993)] CTI 33 MW ITER D2 NBI Momentum injection rate (N) 22 6.5

Technological development required for CTI CW power supplies Must expand from single-pulse to ~ 20Hz CW Initial efforts already underway [Onchi FED 2014] Low-erosion electrodes Electrode coating technology must prevent release of metallic impurities from formation & acceleration electrodes Ensure electrode integrity over millions of pulses before servicing Raman FED 2008

Uncertainties exist for CTI development Basic physics & compatibility to be verified: Will CTI deposition physics hold up when aCTI < aplasma ? Is metallic erosion consistent with high performance ops? Comparison of CT & tokamak sizes (Raman FED 2008)

Maturity of CTI technology for fusion application Decades of experiments, but smaller expert population than NBI CQ Power Supplies: 1-2 years to TRL4 Erosion control: 2-3 year to TRL4 (in parallel with above) Combined: ~2 years TRL5 offline testing to verify impurities in CW After TRL5, ~ 1 year to install on existing mid-sized tokamak for TRL6 Repetitive CT formation circuit [Onchi FED 2014]

High efficiency angular momentum sources would be great benefit to fusion reactor Rotation plays beneficial role in tokamak stability & transport Heating NBI, ⍺, and RF provide minimal torque in reactor-class devices Two viable avenues proposed for angular momentum sources: Low-energy NBI: Mature steady-state technology, but space-charge limits performance & edge coupling physics uncertain Compact toroid injection: Flexible & efficient deposition, but CW technology & erosion control immature Both technologies are feasible for efficiently rotating reactor plasmas