Alcator C-Mod Program

Alcator C−Mod Alcator C-Mod Program

Program Science Objectives Hutchinson 15m Budget, Schedules, and Manpower Marmar 20 MIT Institutional Issues Porkolab 10

OFES Budget Planning Meeting, Gaithersburg, Mar 2003 Program Exploits Unique Features of the Alcator C−Mod C-Mod Tokamak

Major thrusts: Quasi-steady Advanced Tokamak: utilizing long pulse length cf L/R, new LH facility. Burning Plasma Support:

High B; reactor pressure, qk; i-e coupled; Mo PFCs.

Unique dimensional parameters give special relevance to topical science research: Transport: Marginal stability, pedestal, electron transp. Edge/Divertor: SOL transport, Neutrals, Power handling. Wave/Particle: Purely RF driven. ICRF, LH physics. MHD: Active MHD spectroscopy. ICRF/LH stabilization. Momentum Transport Without Sources Alcator C−Mod 4 C-Mod has no beam momentum source 0.3

3 ∼like burning plasma/ reactor. Observes rapid rotation even so. 2 0.6 0.0

m/s) Velocity (shear) crucial ingredient in transport. 4

(10 Key to both transport science and performance. Tor 1 V

4 0 We will continue to im-

prove diagnostics. 3 H-mode

-1 0.50 0.55 0.60 0.65 0.70 0.75 0.80 0.85 2.5 2.0 1.5 2 ITB

And explore the sub- m/s) 1.0 4

0.5 (10

0.0 tle physics. Tor V 1 0.50 0.55 0.60 0.65 0.70 0.75 0.80 0.85 t (s) Velocity profile information shows 0 L-mode momentum diffusing inwards from -1 0.0 0.2 0.4 0.6 0.8 r/a the edge at L-H transition. ITB plasmas have hollow rotation profile.

Just one of many crucial Transport science objectives. Flow and Current Control with ICRF Alcator C−Mod Take advantage of RF-driven character of C-Mod.

RF drive for active control of ﬂow: Mode Conversion Flow Drive? Is it really feasible? C-Mod gives excellent opportunity to ﬁnd out. We are proposing this as one of our Plain English goals.

Mode Conversion Current Drive

Hampered till now by 40 I / P = 0.023 A/W • 4-strap antenna problems 2

) g 30 CD = 0.023 (A/W/m )

• run time limitations inc Picrf = 3MW

Requires asymmetric phasing. / MW 2 20 IRF =70 kA

Current density predicted / m 2 J RF =54 MA / m

well exceeds background. J (MA 10 I p = 0.8 MA Localization may allow NTM control. 2 JOH(0) =14 MA / m 0 0.0 0.2 0.4 0.6 0.8 1.0 Fast-Wave CD also interesting. r/a ICRF Physics and Technology Alcator C−Mod ICRF Physics RF Technology There is fascinating and important physics We need to turn this from an art into a in RF, e.g. mode conversion (to ICW). science if it is to be reliable for a Burning Plasma Experiment.

The tokamak environment is unique in having high B, copious radiation and ionization sources, disruptive eddy forces. Experiments have to be done in situ.

Studies of science of voltage limits and antenna-plasma interactions. Partnership with Computer modeling. Major initiative in load-tolerant match- Innovative diagnostics of waves. ing circuits.

Want on-site technologist participation. Lower Hybrid Upgrade Phase I Alcator C−Mod Construction completion this month. First Plasma Ops Fall 2003.

Leads to Dynamic AT Program • Current Proﬁle Control • Quasi-Steady Advanced Tokamak Plasmas • NTM suppression Lower-Hybrid-Sustained Advanced Tokamak Alcator C−Mod 2003 2005 Power Spectrum control

o 60 o Phase I Phase II 90 o 120 Klystrons (250 kW each) 12 16 o 150

o Source Power (MW) 3 4 180 4 × 24 waveguide grille(s) 1 2 Power density (MW/m2) 70 45

1 2 3 4 5 n Dynamically adjustable nk spectrum controls power deposition and current drive location.

Ip = 0.86 MA Ilh = 0.24 MA fbs = 0.7 Phase II: Investment in launcher yet to be made. )

FY2005 earliest operation. 2

• Total Power required for AT integrated target / m

• Power density reduced for longer pulse J (MA • 2 launchers can have diﬀerent spectra for pro- ﬁle tailoring. r / a MHD topical science Alcator C−Mod Non-axisymmetric control coils. • Error Field Correction • Locked-mode prevention • Magnetic momentum control

Active MHD Spectroscopy • Alfven Mode Physics • MHD/Disruption Detection

Disruption Understanding and Mitigation • Halo measurements • Inﬂuence of divertor structure • Gas jet mitigation Divertor Upgrade Supports Density Control, Alcator C−Mod Long-Pulse Heat-Flux

New upper divertor (04-05) Cryopump • accommodates the cryopump • necessary for ∼double-null plasmas • optimized for pumping • neutral pressures measured

New Outer Divertor (05-06) • Removes toroidal gaps/leading edges • Simpliﬁed geometry, retains diagnostic access • Tungsten-Brush Tiles. ITER technology.

C-Mod Edge/Divertor science is second to none. New Outer Will continue groundbreaking studies on SOL transport, Divertor ﬂuctuations, neutrals, divertor physics ... Diagnostic Upgrades Key to AT, Science Alcator C−Mod Diagnostic Neutral Beam Faraday Rotation Polarimeter Beam loaned from U.Padova. Proposed for implementation during 2005 Gives adequate signal, measurements.

Motional Stark Effect Measured Accuracy (10ms)

Axis

L−mode

Edge Angle Uncertainty (degrees)

Must be returned and replaced. A higher current, long pulse beam is planned. But no beam can penetrate to center of highest ne Alcator plasmas. Similar to ITER plans. Full ne range.

Other important diagnostics for fluctuations, pedestal, wall interactions, ... Summary by IPPA Thrust Area Alcator C−Mod Burning Plasmas • A specific high field, high performance C-Mod thrust • ITER-specific science in pedestals, NTM control, metal wall retention... • ICRF physics and scaled BPX transport scenarios.

Fundamental Understanding • Initiatives in momentum transport and control by ICRF • LH system and Diagnostics for core transport physics • Edge and SOL transport and control q(0) = 5.08 q(95) = 5.98

qmin = 3.30 Conﬁguration Optimization

• Major Quasi-Steady AT thrust using LHCD Safety Factor - q(r) - Factor Safety Materials and Technology • In-situ testing of ITER W-brush technology r / a • ICRF science and technology especially antenna/coupling Alcator C-Mod Budgets, Operations & Schedule

OFES Budget Planning Meeting March 19, 2003

E. S. Marmar Budget Constraints have Led to Significant Underutilization

C-Mod National Budgets and Research Run Weeks 25 21 21 15 17 19 20 13 8 13 Flat Guidance

15 Presidential

10 Appropriation Budget (2004 M$) (2004 Budget 5

0 1999 2000 2001 2002 2003 2004 2005 Fiscal Year FY04 Guidance Allows Significant Increase in Run Time

Guidance Budgets Fiscal Year 2002 2003 2004 2005 Run Weeks 8 13 21 19 Run Hours 270 430 700 630

10% Increments in 2004 and 2005: Increase to 25 Weeks Fiscal Year 2002 2003 2004 2005 Run Weeks 8 13 25 25 Run Hours 270 430 830 830

10% Decrement in 2004 or 2005: Fiscal Year 2002 2003 2004 2005 Run Weeks 8 13 18 16 Run Hours 270 430 600 530 Alcator C-Mod Overview Schedule (March 2003) Calendar Year 2002 2003 2004 2005 2006 2007 2008 Operations ( ) Adv. Tok. ITB Studies Flow Drive LHCD 3 sec 5 sec Active Stab n-control, power, long pulse Active n-control, j-control fboot ≥ 0.7, βn=3, H89~2.5

Burn Plasma Double Null 2MA, 8T Dimensionless Scaling 6MW, H89 ≥ 2, Zeff ≤ 1.5 Support Inner-Wall limited I-rise opt Power/Part Handling Sawtooth/NTM stab Transport Transient Transp. Shear/Flows Self Org. Crit. Zonal/GAM flows Barrier Physics Momentum Transp. Electron Transp. Reynold's Stress T , n Fluct. Inner SOL Fluct. Impurity Sources & Transp. Edge/Divertor e e Neutral Physics Pumping/Particle Control Power Handling

LH Propagation LHCD Compound Spect RF LH/IC Synergies MCICW/MCIBW/MCCD Load-Tol Ant. ω < ωci ICCD

MHD Ped. Stab.Locked-Modes 2MA Disruptions NTM RWM

3 MW LH 2nd Launcher, 4 MW LH 8 MW ICRF, 3 Antennas Real-time matching 2nd Quad ICRF Antenna 8 MW Tunable Inner Div Up IWS Probe Cryopump/Up. Div. Outer Divertor Up Active Wall BP Prototype Facility W Brush Proto Advanced Materials RFX Beam CXRS, MSE, BES Long Pulse Beam Active MHD Ant. Hard X-Ray Imaging Ultra-fast CCD Camera Edge Fluctuation Imaging Reflectometry Up. Polarimetry Tang. HIREX PCI Upgrade Add Horiz Ports PCI 2nd View Thomson Up. MSE Up. ECE Up. Milestones Completed Since March 2002 C-Mod Complete inner wall modifications MAR 02 Measurements of rotation profile evolution NOV 02 Measure current density profile with MSE NOV 02 Compare single-null, double-null and inner-wall-limited discharges NOV 02 Completion of Lower Hybrid fabrication project APR 03

• Unbalanced Double-Null: • Power to lower divertor • Neutral density high in upper divertor (secondary

separatrix)

• Cryopump will go in upper divertor Research Goals (FY03-FY05)

Higher performance plasmas (5 MW ICRF) SEP 2003

Plasma flow control with radio waves (MC-ICRF) SEP 2003

Driving electric current with radio waves (MC-ICRF) SEP 2003

Commissioning of the microwave current drive system (LHRF) FY 2004

Power and particle handling for Advanced Tokamak plasmas FY 2004

Sensing approach to instability using active coils FY 2004

Current profile control with microwaves (LHCD) FY 2005 Sustaining plasma current without a transformer FY 2005 C-Mod is already contributing strongly to ITER

• At least 80% of C-Mod research addressing ITER- relevant issues • 50% of FY03 run time on experiments identified by ITPA Topical Physics Groups • Current emphasis on – ITB operation with no external momentum input – H-Mode and Pedestal databases – Small/No-ELM regimes – High performance with strongly coupled electrons and ions – Dimensionless comparison experiments – Disruption halo-current dynamics Contributions for ITER will expand in FY04-FY05

• Disruptions – Gas jet mitigation with high pressure plasma – All metal walls • Current density profile control – NTM suppression with Lower Hybrid – Sawtooth control/suppression – Advanced Tokamak physics; steady-state scenarios • High power handling with advanced tungsten divertor modules • Co-deposition and hydrogen retention with all-metal walls and PFC’s • Diagnostic development, especially j(r) with high ∫ ndli ITPA Topical Physics Group Proposals Proposal Title C-Mod FY03 C-Mod FY03 Run Days Additional Completed Run Days planned Effects of inside and vertical pellet launch β scaling of confinement in ELMy H-modes 1 Improving the condition of Global ELMy H-mode and Pedestal databases 3 1 Development of hybrid scenario demonstration discharges Development of steady-state demonstration discharges High performance operation with Te ~ Ti 1 2 ITB operation with no external momentum input 8 5 Improved physics understanding of QDB/QH-mode operation Improved understanding of β-limits with ITB operation Development of real-time profile control capabilities Dimensionally similar ITB scaling experiments Simulation and modelling support for T-10 turbulence studies Understanding of pedestal characteristics through dimensionless experiments 1 2

JET/DIII-D pedestal similarity studies Comparative MHD analysis and predictive modelling of type I and type II ELMy H- mode Stability analysis with improved edge treatment 1 Dimensionless identity experiments with JT-60U type II ELMy H-modes in DIII-D

Impact of ELMs on the pedestal and SOL (effect of aspect ratio) Parameter similarity studies (L-H transition, EDA) 1 1 Parameter similarity studies Quiescent H-mode regimes) Scaling of type I ELM energy loss Tritium codeposition 1 Scaling of radial transport 1 ITPA Topical Physics Group Proposals (cont'd) Proposal Title C-Mod FY03 C-Mod FY03 Run Days Additional Completed Run Days planned Disruptions and effect on materials choices 1 Role of Lyman absorption in the divertor Parallel transport in the SOL 1 Pressure and size scaling of gas jet penetration for disruption mitigation Joint experiments on resistive wall mode physics Joint experiments on neoclassical tearing modes (including error field effects) 1

Neoclassical tearing mode physics - aspect ratio comparison Comparison of sawtooth control methods for neoclassical tearing mode suppression Error field sideband effects for ITER Preparation of ITER steady-state scenario Preparation of ITER hybrid scenario Diagnostic First Mirrors Measurement of q(r) 1.5 2 Confined and escaping α-particles and other fast ions Measurements needed to support advanced tokamak operation Development of radiation resistant components and ITER/reactor relevant measurement techniques Total FY03 C-Mod Run Days for ITPA expts 11.5 16 Total FY03 C-Mod Run Days 24 28 Fraction of run days for ITPA expts 48% 57% Highest Priority Upgrades Included in Guidance Budgets (FY04-05)

• Replace borrowed DNB with long-pulse beam • Cryopump (density control for AT program) • Commissioning and operation of LHCD phase I • Construction of phase II LHCD (additional launcher) • Construction of new 4-strap ICRF antenna • ICRF modifications (load tolerance, real-time matching) • Outer divertor upgrade (higher heat load capability) • New Diagnostics and Upgrades – Thomson scatt., Polarimetry, IR imaging, core and edge turbulence Consequences of 10% Cut (FY2004)

• 3 week reduction in research operation (to 18) • Personnel cuts: – 1 scientist, 1 engineer, 1.5 technicians • Critical upgrades deferred – Phase II Lower Hybrid – Advanced 4-strap ICRF antenna – Outer divertor upgrade (power handling) – 5 year AT goal delayed nearly 1 year Highest Priority Increments (FY04B)

• Full utilization: 4 additional weeks research operation (to 25 total) • Increased science effort (1.5 scientists, 1 student) • Increased engineering and technical support • Earlier implementation of ICRF real-time matching systems (for more reliable high power operation) • Increased spatial resolution for polarimeter (j(r) at highest densities) • Faster replacement of obsolete CAMAC and computing resources • Instrumentation upgrades Consequences of 10% cut in FY05 (I) (with 10% cut in FY04 as well)

• 3 week reduction in research operation (to 16) • Almost no progress on phase II Lower Hybrid – Earliest possible implementation of full LHCD power delayed at least to FY08 – close to 2 year delay for 5 year AT goals • Diagnostics deferred/delayed – Polarimeter delayed – IR cameras deferred • Advanced tungsten divertor module tests deferred Consequences of 10% cut in FY05 (II) (no cut in FY04)

• 3 week reduction in research operation (to 16) • Strongly reduced pace for phase II Lower Hybrid – at least 6 month delay in implementation • Bigger impact on other systems – Polarimeter deferred – IR cameras deferred – Tungsten divertor modules deferred – Real-time ICRF matching delayed – Outer divertor upgrade deferred – Vessel upgrade deferred – Spare ICRF FPA tube deferred (schedule risk) Highest Priority Increments (FY05B)

• Add 6 weeks of research operation, to 25 weeks (full utilization) • Increased science effort (2.5 scientist, 1 student) • Increased engineering and technical support • Complete phase II Lower Hybrid, with spare klystrons • Complete ICRF real-time matching

• Add second view for MSE (Er) • Increased participation in science meetings (including ITPA) • Complete polarimeter with increased spatial resolution • Add Li beam polarimeter for edge/pedestal j(r) • Faster replacement of obsolete CAMAC and computers C-Mod National Budgets (k$, Mar 2003 Guidance)

FY03 FY03 FY04A FY04B FY05A FY05B President Approp Guidance (Incr.) Level (Incr.) Research 5,790 5,123 5,889 6,340 5,804 6,739 Operations 11,972 10,483 12,496 13,986 12,586 15,287 Lower Hybrid MIE 419 124 0 0 0 0 International Collaborations 47 47 47 47 47 47 MDSplus 147 145 146 146 146 146 Lower Hybrid Upgrades 0 0 1,485 1,485 1,480 1,995 PPPL Collaborations 2,752 2,442 2,072 2,500 2,072 2,600 U. Tx. FRC Collaborations 936 425 427 540 427 560 LANL Collaborations 99 99 96 110 96 120

Alcator Project Total 22,162 18,986 22,754 25,250 22,754 27,610 Alcator C-Mod Overview Schedule (March 2003) Calendar Year 2002 2003 2004 2005 2006 2007 2008 Operations ( ) Adv. Tok. ITB Studies Flow Drive LHCD 3 sec 5 sec Active Stab n-control, power, long pulse Active n-control, j-control fboot ≥ 0.7, βn=3, H89~2.5

LH Propagation LHCD Compound Spect RF LH/IC Synergies MCICW/MCIBW/MCCD Load-Tol Ant. ω < ωci ICCD

MHD Ped. Stab.Locked-Modes 2MA Disruptions NTM RWM

OVERVIEW

Miklos Porkolab Director

OFES Budget Planning Meeting, March 18,19, 2003 Gaithersburg, MD

OFES Budget Meeting 3/18/2003 PERSONNEL

FY98 FY99 FY00 FY01 FY02 FY03 Undergraduate Students 6 7 6 5 9 17 Graduate Students 49 48 44 54 49 56 Faculty/Sr. Academic 18 18 18 16 18 18 Visiting Scientists & 57 59 58 54 61 58 Staff Engineers Engineering/Scientific 76 68 65 68 72 68 Research Staff Administrative Staff 13 13 10 12 13 12 Support Staff 14 13 11 9 10 13 Technicians/Drafters 36 29 28 30 30 31

TOTAL 269 255 240 248 262 273

OFES Budget Meeting 3/18/2003 FY 03 OFES Funding by Division

Total funding: $22,617,000

OFES Budget Meeting 3/18/2003 PSFC BUDGET PROJECTION

OFES Budget Meeting 3/18/2003 Total Enrollment of Graduate of Students at the PSFC, by Year

OFES Budget Meeting 3/18/2003 Graduate Student Applicants Double for the Fall of 2003

Physics:

40 new applicants with first choice in plasma physics, and another 40 with second or 3rd choice in plasmas; more than 80 % US citizens Nuclear Engineering:

34 applicants, about 40% US citizens Research Assistant positions available:

9 in experiment, none in theory, only 6 OFES funded

OFES Budget Meeting 3/18/2003 Employment Status of MIT PSFC Students upon Graduation 1980–2002

183 Students

Research Lab Unknown (National/Private) 19 57

Industry Business 40 12

Fusion MS Degree (MFE & ICF) (mostly to Academia 40 industry) 40 100 OFES Budget Meeting 3/18/2003 Vigorous K-12 Outreach Program in Plasma Science (Internally Funded)

y The Mr. Magnet Program (Paul Thomas) reaches over 30,000 students per year. y The Center provides over 35 tours of the Center per year, reaching over 800 K-12 students, teachers and general public. y MIT PSFC supports growing APS-DPP education activities, and prepares to lead these outreach efforts in 2004 in Savannah, GA. y PSFC helps maintain and expand Coalition for Plasma Science educational activities, including website and publications.

OFES Budget Meeting 3/18/2003 ALCATOR C-Mod ADVANCED TOKAMAK A National Facility z Advanced Tokamak (AT) Program: Quasi-steady state configuration at B~5T with high bootstrap current fraction and RF current and profile control [FESAC MFE Goal #3 -AT] « Add 3(4) MW of lower hybrid (4.6 GHz) power z Burning Plasma Relevant, RF heated plasma regimes at reactor 20 -3 relevant magnetic fields (5-8T) and densities (ne ~ 2 - 4 x 10 m ), with metallic plasma facing components [FESAC MFE Goal #3 - Burning Plasma Physics] « 8 MW ICRF installed for heating and flow drive z Typically 20 + graduate students doing Ph.D. theses z Increased funding needed for FY 2004, 2005 for 21 (24) weeks of operation; complements DIII-D, and prepares the US to optimize, and to take full advantage of future ITER operations OFES Budget Meeting 3/18/2003 PHYSICS RESEARCH DIVISION OFES FUNDED EXPERIMENTS

A. Levitated Dipole Experiment (LDX) (J. Kesner - MIT; D. Garnier, M. Mauel - Columbia University) New proposal to be submitted this Spring B. Advanced Diagnostics -Each Experiment funded through FY 05 • Phase Contrast Imaging (PCI) (DIII-D, C-Mod collaboration) (M. Porkolab, C. Rost, Grad students) • CTS from energetic ICRF tails (TEXTOR, ASDEX-U collab.) (P. Woskov, Post-Doc) • TAE modes in the presence of alphas and ICRF tails (JET collab.) (A. Fasoli, J. Snipes, Post Doc) C. Driven Magnetic Reconnection Experiments on VTF (Dr. J. Egedal + 2 grad students + 2 undergrads; Prof. A. Fasoli on leave) -Experiment funded internally; proposal submitted to NSF/DOE initiative in January; substantial student and Phys. Dept. interest, only “Laboratory Basic Plasma Physics Experiment” at the PSFC; (Previously funded by Prof. Fasoli’s DOE Junior Faculty Award;

OFES Budget Meeting 3/18/2003 LDX COMPONENTS NEAR COMPLETION

z Base diagnostics, power supplies, and ECRH being installed at MIT

z Nb3Sn Floating Coil with final super-insulation being installed at Ability Technology z NbTi Charging Coil tested at SINTEZ (Russia) in March

z Fusion’s first High Tc coil completed for the LDX Levitation Coil Charging Coil LDX Cell (SINTEZ, RF) z First plasma this summer

Levtion coil Floating Coil (Ability) Levitation Coil OFES Budget Meeting 3/18/2003 (Everson Elec.) Collisionless Reconnection Processes in VTF

Toroidal magnetic cusp of VTF Poloidal field coils Ψ (b) 0.5 |B| (mT)

150 120 ECRH ring: 87.5 mT Z (m)

60 120 30 0

Ceramic window

2.45 GHz horn antenna −0.5 Four additional Poloidal field coils turns on port

0.5 1 1.5 2 R (m) The Versatile Toroidal Facility (VTF)

Example of experimental measurements providing detailed information on the time evolution of the plasma density, current and electrostatic potential during reconnection.

OFES Budget Meeting 3/18/2003 PHYSICS RESEARCH DIVISION THEORY (P. Catto, Head)

A. Edge Physics,Turbulent Transport, Divertor Theory, ITER (P. Catto, D. Ernst, Prof. K. Molvig, A. Simakov (post-doc)) B. Advanced Tokamak, LDX, MHD Stability, ITER, Computational Physics (P.T. Bonoli, Prof. J. Freidberg, J. Kesner, J. Ramos, J. Wright) C. Current Drive, Nonlinear Dynamics, EBW on NSTX, RF Heating on Alcator ( P.T. Bonoli, A. Ram, Profs. A. Bers, M. Porkolab) ISSUE: Post-Doc Simakov being let go due to budget shortfall; Profs. Kim Molvig (recently returned to fusion research) and Jeff Freidberg (stepping down as Nucl. Eng. Dept. Head) need summer salary and travel funds ($ 200k) starting in FY 03, as well as support for 2 students in FY 04 ($100k ) and 2 more students in FY 05 (+$100k) OFES Budget Meeting 3/18/2003 Technology & Engineering Division Issues at the PSFC z 6 years of flat funding eroded by inflation leads to significantly reduced effort and capability. • Inadequate funding for small-scale experiments, operating test facilities, or maintaining equipment • No funding available for development of advanced SC materials z Division core capability has been maintained since 1999 by >40% non-OFES Work-for-Others z Recent effort applied to ITER cost study is virtually unfunded compared with level of effort required. • Reengagement in ITER magnet activities requires substantial ramp- up in funding : • $2M in FY 2004 • $4M in FY 2005

OFES Budget Meeting 3/18/2003 FY02-03 Accomplishments of the Magnet Technology Program

Model Coil Testing Superconducting Magnets Quadrupole Magnets and for LDX Cryostat for HCX

Nb3Al Coil NbTi Tested at Charging JAERI Coil

Optimized Nb3Sn Floating Quadrupole Coil

TFMC Tested at FzK

HTS HCX Levitation Cryostat Coil

OFES Budget Meeting 3/18/2003 ECH Technology Issues z Program needs to be strengthened to meet commitments to the base program and ITER z Base program research tasks: • Prototype 1.5 MW, 110 GHz highly reliable gyrotron • 1 MW, 15 GHz gyrotron design for EBWH on NSTX • Future gyrotron development: frequency tunability; higher efficiency, power and frequency availability • High efficiency transmission lines and mode converters z ITER research: • 1 to 1.5 MW, 170 GHz gyrotron development for ITER z Additional funding requested: $250k in FY04, $500k in FY05

OFES Budget Meeting 3/18/2003