OFES FY2011 Work Proposal Video-ConferenceApril 21, 2009

Alcator C-Mod Highlights, Plans, and Budgets

Research supported by U.S. Department of Energy, Office of Fusion Energy Sciences

OFES FY2011 Work Proposal Video-Conference

April 21, 2009

Alcator C-Mod Highlights, Plans, and Budgets

Research supported by U.S. Department of Energy, Office of Fusion Energy Sciences

Compact high-performance divertor tokamak research to establish the plasma

physics and engineering necessary for a burning

plasma tokamak experiment and for

attractive fusion reactors.

ScienceChallenges

Energy, Particle& Momentum

Transport

PlasmaBoundary

Interactions

Wave-PlasmaInteractions

MacroscopicStability

IntegratedScenarios*

ITER

*Equilibrated electrons-ions, no core momentum/particle sources, RF Ip drive

ITER BaselineInductive High Pressure

Advanced ScenariosHigh Bootstrap

Quasi-Steady State

H-ModePedestal

GAPInitiatives

DEMO

C-Mod Unique in World and USAmong High Performance Divertor Tokamaks

Unique in the World:• High field, high performance divertor tokamak• Particle and (usually) momentum source-free heating and

current drive• Equilibrated electrons and ions• Solid high-Z plasma facing components• ITER level Scrape-Off-Layer/Divertor power density• Approach ITER neutral opacity, radiation trapping• Highest pressure and energy density plasmas

Exclusive in the US :• ICRF minority heating• Lower Hybrid Current Drive• Premier major US facility for graduate student training

C-Mod Plays Major Role in Education of Next Generation of Fusion Scientists

• Typically have ~25-30 graduate students doing their Ph.D. research on C-Mod (more students than scientists)– Nuclear Science & Engineering, Physics and EECS (MIT)– Collaborators also have students utilizing the facility– Current total is 31 (30 full-time on-site)– Fully involved in all aspects of our research, leading many

of the experiments as session leaders• MIT undergraduates participate through UROP program• Host National Undergraduate Fusion Fellows during the

summer

Collaborators are key participants in all aspects of the program

DomesticPrinceton Plasma Physics LabU. Texas FRCU. AlaskaUC-DavisUC-Los AngelesUC-San DiegoCompXDartmouth U.General AtomicsLLNLLodestarLANLU. MarylandMIT-PSFC TheoryNYUORNLSNLAU. Texas IFSU. Wisconsin

InternationalASIPP/EAST HefeiBudker Institute NovosibirskC.E.A. CadaracheC.R.P.P. LausanneCulham LabENEA/FrascatiFOM Nieuwegein, NetherlandsIGI PaduaIPP GarchingIPP GreifswaldITER Organization CadaracheJET/EFDAJT60-U, JAEAKFA JülichKFKI-RMKI BudapestKSTAR KoreaLHD/NIFSOxford U.Politecnico di TorinoU. Toronto

Coordination: USBPO, TTF, ITPA

Completing Major Maintenance and Refurbishment of the Tokamak Facility

• Core tokamak disassembled– Complete renewal of

TF coil sliding joints– Numerous other

upgrades, improvements

• Reassembly is well underway– Scheduled pump-

down in May

Alternator Rotor Re-Certification has been Successfully Completed

• After 2008 inspection, OEM recommended “do not return the rotor to service”– Expressed concerns about

density of ultrasound indications, and possibility of sudden fracture

– This, in spite of also saying there was no significant change over 3 inspections (’96, ’03, ’08)

• Working with MIT’s Vice-President for research, PSFC Scientists and Engineers, and 2 industry expert companies, embarked on extensive program of testing to re-evaluate the OEM recommendation

Results of testing and evaluation all positiveRotor has been approved for operation

• All materials tests have shown that the rotor steel has good properties, well beyond those used in the conservative assumptions of industry specialists

• Two independent outside expert analyses have certified that the rotor is fit for continued safe service

Considering the rotor alone, operation for 20 calendar years (or 2000 run days) before the next boresonic inspection is recommended

• A panel of 3 experts (outside of the C-Mod group) recommend return to service

• MIT VP for Research concurs• Reassembly is scheduled to begin April

27, and is not expected to delay the start of the FY09 campaign

KJ-IC = 135 ksi*sqrt(inch)

FY09 Budget Implications of Rotor Re-Certification

• Previously unanticipated costs in FY09 (~$1.0 M)– Complete reinspection, materials samples, analysis

• Actions– 1 year delay in procurement of 3 new Lower Hybrid

Klystrons– 9 month delay in construction of advanced 4-strap

ICRF antenna– Personnel decreases (1 scientist, 1 technician)*

• First priority for Stimulus increment is to restore these cuts

*Through attrition

Facility Plans and Major Enhancements

16x4 wave guide array

individual alumina windows

novel 4-way splitters

Standard waveguide and flanges• Lower Hybrid upgrades– Replace first launcher with

advanced low-loss design (’09)• Increased net power

– new + spare klystrons (’10-’12)– Additional launcher and 4’th

MW (’11)

Facility Plans and Major Enhancements

• ICRF upgrades– 2 new 4-strap antennas

(’09 and ’10)• Rotated/aligned with B

– Reduce/eliminate sheath induced sputtering

– Fast-Ferrite Tuners for all 4 transmitters (real time adaptive tuning) (’12)

– Power supply/control upgrades (improved reliability) (’13)

– Tuneability (40 – 80 MHz) for 3rd and 4th transmitters*

*Upgrades requiring incremental funding shown in blue

Facility Plans and Major Enhancements(cont’d)

• Outer divertor upgrade – DEMO-like divertor (’11)– Continuous vertical plate (higher power/energy handling)– Tungsten lamella plate design– Controlled temperature (≤ 600 0C)

• Hydrogen isotope retention studies• Non-axisymmetric coil upgrade (increased toroidal mode number

flexibility, resonant magnetic perturbation) (’13)• Massively parallel computing cluster upgrade (’12)• Magnet power supply upgrades (poloidal field) (’10 and ’13)

– Improved control at high current, high elongation, long pulse• Boron coating of RF protection, outer shelf, and secondary limiter

tiles (’09)

Major Diagnostic Enhancements/Upgrades2009-2013

• Polarimetry (PPPL, UCLA) [j(r), ne(r), magnetic fluctuations] (’09, ’10)• MSE upgrade (PPPL) [eliminate stress birefringence (’09); more radial

channels(’11)]• Heterodyne ECE upgrade (U. Tx.) [improved views] (’09)• SOL Thomson scattering (’10)• Compact Neutral Particle Analyzer [multiple chords] (’09)• Lower Hybrid launcher reflectometer (ORNL) (’09)• ICRF antenna reflectometer (ORNL) (’10)• In-situ accelerator* [first wall analysis] (’11)• SPRED survey spectrometer (LLNL) (’09)• Fast-ion loss detector (’13)• IR camera upgrade (LANL) [divertor heat loading] (’09)• Gas puff imaging upgrades (PPPL) [edge fluctuations] (’09, ’11)• Vertical viewing high harmonic ECE [LH-driven fast electrons] (’11)• Synchrotron imaging [runaway electrons] (’13)• CO2 scattering [fluctuations, waves] (’10)

*Primarily funded through OFES Diagnostic Initiative

C-Mod physics regimes, machine capabilities and control tools uniquely ITER-relevant in many respects:

• Edge and Divertor: All high-Z solid plasma facing components (key for D retention, effects on core). Divertor characteristics close to, or same as ITER (power flow, neutral and radiation opacity).

• Core Transport: Equilibrated ions and electrons. No core fuelling, normally no momentum sources (expected to be very low on ITER).

• Macro-stability: Can access ITER β range, as well as same BT and absolute pressures (important for disruption mitigation).

• Wave Physics: Similar tools (ICRF and LHCD) to ITER. Same B, n => same ωp, ωc, similar ω (key for Waves, LH feasibility).

• Pulse length: τpulse >> τCR (exceeds ITER). Adding non-inductive CD capability (important for Steady State scenarios).

Combination of these features is unique and enables integrated studies of many key questions.

0.0

C-Mod Addresses Critical Issues for ITER• Integrated Scenarios:

– Breakdown and current rise (li, flux consumption, vertical stability)

– Reference ITER scenarios for databases and modeling– ITER hybrid scenarios: experimental development,

understand mechanisms for maintaining q0>1– Profile control methods: especially j(r) with LHCD+bootstrap– Integration of all regimes with ultra-high edge heat flux

• Core Transport:– Regimes with equilibrated e-i, low momentum input, dominant

electron heating– Collisionality dependence of density peaking– Develop common technologies for integrated modeling

(frameworks, code interfaces, data structures): MDSplus is a model

• Pedestal Physics:– L-H power threshold at low density (at ITER B, high neutral

opacity)– Improve predictive capability for small ELM and quiescent H-

mode regimes; small ELM regimes for βN>1.3; shaping– ELM control: stochastic fields with external coils

• Wave-Plasma Interactions:– LHCD physics and coupler technology– ICRF heating, current and flow drive

. .

-8

-6

-4

-2

0

2

4

6

8

0 1 2 3 4 5 6 7 8 9 10 11 12 13

Z, m

R, mC

S3U

CS2

UC

S1U

CS1

LC

S2L

CS3

L

PF1PF2

PF3

PF4

PF5PF6

g1g2

g4

g3

g5

g6

C-Mod Addresses Critical Issues for ITER• Plasma-Boundary Interactions

– Tritium retention and removal: solid high Z PFCs; plasma and nuclear effects; surface modification

– Surface effects: ICRF-related impurity generation; boronization

– Power handling and impurity control: SOL transport; radiative/detached divertor.

• Macrostability:– Disruption database (energy loss, halo current): excellent

diagnostics (radiated power, surface heating, erosion, runaways)

– ITER applicable disruption mitigation, validate 2 and 3-D MHD codes with radiation: pioneering studies of C-Mod experiments with NIMROD/KPRAD; LH tool to seed non-thermal electron population

– Develop reliable disruption prediction methods: developing robust algorithms; real-time automatic mitigation implemented in Digital Plasma Control System

– NTM physics: effects of rotation; LHCD control/stabilization; sawtooth control

– Understand intermediate n AEs; damping and stability of AEs; active MHD antennas couple to intermediate n modes.

– Redistribution of fast particles by AEs: ICRF ion tails drive AEsunstable; excellent diagnostics (PCI, CNPA, lost ion detector)

C

G

D

Trajectories of1 MeV deuteron beam fromRFQ accelerator

B=0 T

B=0.

44 T

sepa

ratr

ix

gamma orneutrondetector

NIMROD/KPRAD Simulation:Mitigated C-Mod Disruption

0.8 ms 1.6 ms

RFQ In-Situ Surface Analysis

Joint Experiments Coordinated through ITPA

• Many issues (especially for ITER) studied in close coordination with other tokamak facilities

• Current areas of emphasis on C-Mod– H-mode access/hysteresis (TC-2, TC-3, TC-4)– Transport dependence on ExB shear and momentum (TC-6)– Intrinsic rotation (TC-9)– ITG/TEM/ETG turbulence (TC-10)– Helium transport (TC-11)– ITG critical gradient and profile stiffness (TC-13)– RF driven flows (TC-14)– Momentum and particle pinch dependence on collisionality (TC-15)– Deuterium deposition, retention (DSOL-13, DSOL-17)– SOL transport, blobs, fueling (DSOL-5, DSOL-15, DSOL-16)– Divertor reattachment (DSOL-20)– Disruption mitigation, database, runaways, avoidance (MDC-1, MDC-15, MDC-16, MDC-

17)– NTMs, Sawteeth (MDC-5, MDC-8, MDC-14)– Error fields (MDC-6)– TAE studies (MDC-10, MDC-11, EP-2)– Non-resonant magnetic braking (MDC-12)– Vertical stability and performance limits (MDC-13)– Resonant magnetic perturbations, ELMs and pedestal (PEP-19)– Pedestal structure, width (PEP-6, PEP-20)– Pedestal control with RF (PEP-22)– Small ELMs (PEP-16)– Steady-state scenarios (IOS-6)– Hybrid scenarios (IOS-4.1, IOS-6)– ITER demo discharges (IOS-1.1, IOS-1.2, IOS-2.2)– ICRF coupling (IOS-5.2)

C-Mod Affiliated Scientists Fully Engaged in Community Activities: BPO, ITPA, ReNew

• ReNew Theme I — Burning Plasma– Extending confinement to reactor conditions: Jerry Hughes, Dave Mikkelsen,

John Rice, Bill Rowan– Self-heated plasma: Ron Parker (lead), Chuck Kessel, Steve Wukitch– Control and sustainment (joint with Theme II): Steve Wolfe– Mitigating transient events (joint with Theme II): Bob Granetz, Val Izzo, Dennis

Whyte– Diagnosis (joint with Theme II): Jim Terry (lead), David Brower

• ReNew Theme II — High Performance, Steady-State– Amanda Hubbard (Theme Chair)– Auxiliary systems: Randy Wilson (Lead), Miklos Porkolab– Integration: Chuck Kessel, Bruce Lipschultz– Validated predictive modeling: Martin Greenwald, John Wright– Magnets: Joe Minervini, Leslie Bromberg, Joel Schultz– Off-normal events (joint with Theme I): Bob Granetz, Val Izzo, Dennis Whyte

• ReNew Theme III — Plasma-Material Interface– Plasma-wall interactions: Brian LaBombard– Plasma facing components: Bruce Lipschultz– Internal components: Jim Irby, Randy Wilson, Dennis Whyte

• ReNew Theme IV — Harnessing Fusion Power– Safety: Catherine Fiore

• ReNew Theme V — Optimizing the Magnetic Configuration– Stellarator: Jeff Freidberg

Core Transport – Major Themes

• Overarching: Model Testing and Code Validation

– Systematic and quantitative comparisons with nonlinear turbulence codes

• Use synthetic diagnostics (e.g. GYRO/PCI)

– Quantitative where codes and models are more mature

• Role of magnetic shear (exploit LHCD) • Electron transport (esp. at low ne)

• Particle and Impurity Transport– How to predict fueling, density profile and

impurity content? – Adding laser impurity injector (multi-pulse)– Now within capabilities of gyrokinetic codes

• Flows and Momentum Transport– State of the art diagnostics (with PPPL)– ICRF and LH can each drive rotation– Correlations with turbulence

• Internal Transport Barriers– Access conditions and control, especially in

absence of dominant ExB– Use LHCD to trigger by mod. of shear

Rotation strongly influenced by addition of LHCD

0.70 0.75 0.80 0.85R (m)

-30

-20

-10

0

10

20

30

40

VTo

r (km

/s)

0.6-0.7 s

1.3-1.4 s

0.9-1.0 sH-mode

H-mode + LHCD

L-mode

Pedestal Physics – Major Themes(Joint OFES Milestone, FY2011)

• Pedestal structure and transport– Effects of shaping, topology, shear on width

(joint with DIII-D, NSTX)– Momentum transport– Gradient limits, ELMs

• Collisionality, topology– Connection to L-mode pedestal

• Edge relaxation mechanisms– Pedestal regulation with/without ELMS

• L-H transition– Low density threshold scaling– Helium majority plasmas– Slow (2-phase) transitions

• “improved” L-mode• Pedestal control

– Shaping, topology– External fields (RMP)– Applications of RF

• LHCD can strongly modify the pedestal• Theory and simulation

– Role of ER– Turbulence and transport (BOUT, XGC1)– ELM/EDA studies (ELITE, M3D)– Integral part of the ’11 joint milestone

DIII-D scaling

In collaboration with P. Snyder (GA)

1.0

1.5

2.0

2.5

3.0

0 100 200 300

H89

EDAELM-free

Er Depth (kV/m)

R. McDermott, Phys. Plasmas(forthcoming)

Energy Confinement Strongly Correlates with Depth of Er Well

β Scaling of Ped. Width on C-ModType I ELMy H-mode

Plasma Boundary – Major Themes

• Transport - central as it controls heat loads, impurities (FY10 Joint OFES milestone)– Perpendicular transport

• Time-averaged, turbulent– Parallel heat transport– Divertor physics– Adding suite of SOL/surface

diagnostics• Plasma-surface interaction - Crucial

information for a reactor (high-Z tiles)– Fuel retention (FY09 Joint OFES

milestone)– Effects of RF waves/sheaths on the

edge– Material properties and surface

conditioning• First-wall development towards fusion

DEMO– Molybdenum and tungsten tiles– DEMO-like W divertor (≤ 600 0C)

• Being designed in collaboration with PPPL

Waves-Plasma Interactions– Major Themes

• Flow Drive– ICRF and LHRF both demonstrated

• Mode-conversion ICRF – both toroidal (co-) and poloidal drive

• LHRF – counter-current toroidal drive

• Current Drive– LHRF: efficient far off-axis current drive

• More power, longer pulse (in stages)

– ICRF: core current drive (seed current), and applications to sawtooth control

• Lower Hybrid physics at ITER-relevant parameters– Same wave, plasma, and cyclotron

frequencies• Coupler and Antenna Technology

– Advanced low-loss LH coupler, load tolerant splitter

– B-aligned ICRF antenna to reduce sheath effects

• Model development and validation– State of the art predictive models,

scalable to ITER and reactors– Work closely with RF-SciDAC

ICRF Mode-Conversion Flow Drive

Y. Lin, et al., Phys. Rev. Lett. 101, 235002 (2008).

0

40

80

1

3

0.8 1.0 1.2 1.4 1.6t [s]

1

3

D( He) Mode ConversionD(H) Minority Heating

3

V (r=0) [km/s]

<n > [10 m ] e-320

T [keV]

P [MW]

e

rf

φ

Macroscopic Stability – Major Themes

• Disruption avoidance/mitigation– Real-time anticipation/action

• Extend to locked modes, density limit, high β

– Runaway electron amplification/suppression

• LHCD for fast e- seed• Effects of shaping (κ)

– Advanced MHD simulation• Non-Axisymmetric Fields

– Magnetic Braking (NTV theory)– RMP ELM investigations (n=1)

• Planned upgrades to A-coil power supplies (higher δB, also n=2) (’13)

• Vertical Stability– Important ITER operations issue– Testing high order controllers,

Kalman filters, “Safe” scenarios• Alfven Eigenmodes

– Active probing of stable intermediate toroidal mode number modes

– ICRF fast-ion induced instabilities– PCI diagnostics, NOVA-K modeling

(with PPPL)

(a) (b)

TAE eigenfunction comparisons:q-profile is varied to get best fit

Integrated Scenarios for ITER and Beyond

• By demonstrating high performance plasmas similar to the plannedITER baseline scenario (H-Mode) and advanced scenarios (also relevant to DEMO), with relevant parameters and control tools, C-Mod will address many of the same challenges as ITER.– Integrates elements of all of the science topical areas

• For the inductive H-mode regime (q~3, βN=1.8), these include pedestal issues, high heat fluxes and RF-wall interactions.

• For the hybrid scenario (q~4, 50% non-inductive), we will assess whether improved confinement is still achieved in torque-free plasmas and with RF current and flow profile control.

• Steady-state regime aims at full non-inductive CD, with progressively increasing bootstrap and βN, staying below no-wall limit (~3). As on ITER, achieving this requires both full power and high confinement. – Will demonstrate far off-axis LHCD at same B, ne , similar

frequency proposed for ITER– Pulse length capability of 5 to 10 current relaxation times for

fully relaxed current profiles

ITER H-Mode Baseline Scenario – Major Themes

• ITER-like H-mode regimes– Same pressure, β, field, Zeff, shape– Particle source free (RF actuators)– Active flow drive

• Divertor and wall materials and conditioning– High heat flux– Hydrogenic retention– Impurity/particle control– Core-boundary compatibility

• ITER-relevant plasma control– Similar configuration/coil-set, advanced

control system• I ramp-up, ramp-down• Operating point control• Benign fault handling

• Transport and stability– Benchmark modeling– Evaluate disruptivity/stability issues– Pre-nuclear phase (e.g. H-mode access)

ICRF heating during Ip rampReduces li and flux consumption

li(3) @ 0.5s (end of current rise)

0.85

0.9

0.95

1

1 2 3 4Te0 [keV], av. 0.3-0.5s.

Ohmic

ICRH

V-s

requ

ired

Time [s]0.2 0.4 0.6 0.8 1.0

0.5

1.0

1.5

inductive

2MW ICRH

Ohmic

TSC/TRANSPresistive

rise flat top

Advanced Scenarios – Major Themes

• Develop operational scenarios for ITER and beyond– Hybrid (facility milestone ’09)– Non-inductive ‘steady-state’

(very long pulse relative to skin time)

– ITB and double-barrier regimes

• LHCD current density profile control key to many of these studies

• Compatibility of all scenarios with pedestal, SOL and divertor

• Integrated modeling essential to guide the research

ICRF onlyICRF + LHICRF onlyICRF + LH

Te

Ti

T e ,T

i (keV

)P

e (kP

a)n e (1

020

m-3

)

Rmid (m)

LHCD influences PedestalDecreased n and ν, increased T, P

Contributions to “Gap” Issues

• Recent FESAC panel identified critical “gaps” on the path from ITER to DEMO that will require new initiatives– Assumes successful resolution of many issues first on existing

facilities and ITER• C-Mod helping to resolve many of these key issues

– Plasma facing components: high Z metals, ultra-high SOL power densities.

– Off-normal events: disruption avoidance, prediction and mitigation.– Plasma-wall interactions: SOL and divertor transport,

erosion/redeposition, hydrogen isotope retention.– Integrated, high performance plasmas: focus of integrated thrusts.– Theory and predictive modeling: code benchmarking, discovery of

new phenomena, iteration of theory and comparison with experiment.– Measurements: new and improved diagnostic techniques.– RF antennas, launchers and other internal components:

advancing the understanding of coupler-edge plasma interactions, improvement of theory and modeling.

– Plasma modification by auxiliary systems: RF (ICRF and LHRF) for current drive, flow drive, instability control; ELM control

– Control: maintaining high performance advanced scenarios with fully relaxed current profile.

Validation: Comparing State of the Art Code Resultswith C-Mod Data

• Pedestal, Edge and Boundary– XGC code being developed through SciDAC FSP

Prototype Center• prediction of pedestal height and width

– GEM, BOUT, ESEL, KN1D – ELITE for MHD stability of intermediate to high n

ballooning modes• Waves

– (TORIC, AORSA) + (CQL3D, ORBIT RF, LSC) for minority tail evolution, ICH, LHCD, MCEH, MCCD, FWEH, FWCD, ICCD

• Synthetic diagnostic comparisons with PCI, hard X-ray and CNPA measurements.

– TOPICA + (TORIC) for comparisons with antenna loading and antenna electrical characteristics

– TOPLHA for evaluating LH Launcher coupling and design.

• Macroscopic Stability– NIMROD + KPRAD - simulate gas puffing– M3D - sawtooth reconnection and NTM

stabilization– NOVA-K to simulate Alfven cascades

• Synthetic PCI diagnostic implemented• Transport and Scenario Modeling

– GS2, GYRO – Transport, barrier simulations (internal and edge)

– TSC-TRANSP simulations for AT scenario development

– STRAHL for impurity transport

Fluctuations in H-mode (~400kHz) agree with predictions for ITG from

GYRO

Freq: [300, 500] kHz

GYRO Simulation:

PCI Measurement:

Nn: 16; n:10 Nn: 28; n: 5

Wavenumber [cm-1]-15 -10 -5 0 5 10 15

0.2

0.4

0.6

0.8

Aut

opow

er [1

032m

-4/c

m-1]

0.0

1.0

trange: [0.85, 0.95] sec shot: 1080516005

Wavenumber [cm-1]-15 -10 -5 0 5 10 15

10

100

200

300

400

500

Freq

uenc

y [k

Hz]

[1032

m-4/c

m-1/H

z] 10-3

10-5

10-72πf/k

~ 4

km

/sec

Milestones

• OFES Programmatic Joint Targets– FY08: Rotation/Momentum transport (complete)– FY09: Hydrogenic retention (C-Mod emphasis on high-Z)– FY10: Scrape-Off-Layer/Divertor power flows– FY11 (anticipated): Pedestal Physics

• C-Mod Facility Targets (Plain English Goals)– FY09

• Self-generated plasma rotation• Hybrid advanced scenario investigation

– FY10• Testing model of fuel retention in first-wall• Runaway electron dynamics during disruptions• Accessibility conditions for small ELMs

– FY11• Investigate ICRF sheaths and impurity generation with

advanced field-aligned ICRF antenna• Characterize the H-mode pedestal

Detailed planning for the FY09 campaign is underway — Ideas Forum held April 6-8

Very Successful Ideas Forum (April 6-8)Many new ideas proposed

• Final tally = 137– Comparable to previous IF– Proportion of ideas

submitted under each topic also similar

• Contributions from collaborators: 27%– up from FY07 – Domestic, international

contributions– ITER Organization

• 28% of submissions were from students

• Follow up and prioritization happening now

DD, Ops, Basic Sci.,

12

MHD, 9

Adv. Scenarios,

10

ICRF, 10

LH, 12Transport,

38

Divertor + Edge, 28

H-mode Scenarios,

18

Major Facility UpgradesCalendar Year

Facility

2008 2009 2010 2011 2012 2013

Inspect: Tokmak & Altrntr.

EFC upgrade (higher κ) EF2 upgrade

Lower Hybrid

advanced low-loss launchers launcher gas-puff

ICRF new 4-strap antennas fast-ferrite tuners

+4 MW tunableantenna reflectometer

Boundary

Complete Guidance Proposed Budget

additional klystrons

4 MW source

additional klystron

fast-ferrite prototype

Tungsten lamella tiles

Digital Plasma Control

120 MHz

Demo-like divertor (600 C)

cryo upgrade

ECDC upgrade (add vertical B)

new Beowulf

A-Coil Upgrade

Improved PFCs

transmitter protection up

Beowulf upgrade

additional klystrons

power supply up

coupler reflectometer

Boron-coated tiles

4 MW source

Operations GuidanceIncremental

15.7 1011

1318

1318

Major Diagnostic UpgradesCalendar Year 2009 2010 2011 2012 2013

Guidance Proposed Budget

MSE upgrades j(r)

SOL Thomson

Polarimeter: 3 channel 10 20 channel 20 Channel

Divertor probe arrays

Cf neutron source

Fast ion loss

Runaway electron

Radial correlation reflctmtr Doppler reflectmtr

CNPA up.

LH SOL reflctmtr ICRF SOL reflctmtr

CO2 scatt.

SPRED spectrmtr

Accelrtr surface analysis

IR Camera up.

Upper Div. T.C.

Fast Diode Up. New GPI Views

High Harmonic ECE

VUV Spectrmtr Up. CXRS Fast Ion

DNB Pwr/Contr up

Research Goals (FY09-FY11)

FY 2011Tests of advanced field-aligned ICRF antenna

FY 2010Characterize accessibility conditions for small edge-localized modes

FY 2010Study of runaway electron dynamics during disruptions

FY 2009Self-generated plasma rotation

FY 2009Hydrogenic retention (joint milestone with DIII-D and NSTX)

FY 2010Testing a model of the fuel retention process in first-wall tiles

FY 2009Hybrid Advanced Scenario investigations

FY 2011Characterization of the H-mode pedestal

Budget Profiles (k$)

22,905(6)

90

320

2,910

19,585

FY11D*

28,262(18)

110

450

3,802

23,900

FY11B

24,781(10)

100

340

3,372

20,969

FY09

25,606(13)

24,981(13)

National Project Total(research run weeks)

100100LANL

350340U Texas

3,4563,372PPPL

21,70021,169MIT

FY11A*FY10A*Institution

Appropriation Guidance Base Increment -10%

*Reductions in ForceFY10A: 1 Scientist, 1 TechnicianFY11A: 1 Scientist, 1 TechnicianFY11D: 3 Scientists, 2 Students, 2 Post-Docs, 3 Engineers, 1 Technician

ARRA Stimulus Funding

• Stimulus funding would be applied to high priority facility upgrades and increased run time in FY09 and FY10– Increase total of 6 research run weeks (to 11 in FY09, 18 in

FY10)– Restore cuts to Lower Hybrid and ICRF

• Re-instate order for 3 new klystrons• Advanced 4-strap ICRF antenna back on schedule• Additional new klystrons (for full complement of 4 MW

source)• ICRF FFT matching systems• Completion of LHCD 4’th MW 1 year earlier

– Divertor diagnostic upgrades• Particularly enhance contributions to FY10 joint milestone

– DNB power supply upgrades (increased availability/reliability)

Incremental Funds for C-Mod in FY09-11 would Enable Significantly Extended Scientific Progress*

Simulations of pedestal structure

Slow L-H transitions, improved L-modes

Influence of neutral fueling/ionization

Low density H-mode threshold

Shaping and pedestal regulation

Pedestal Physics

Shear modification of core barriers with LHCD

Combined high power ICRF/LHCD

Advanced Scenario modeling

Internal Transport Barriers with LHCD

Hybrid scenario feasibility with LHCD

Advanced Scenarios

High power handling of tungsten divertor

Control algorithms mimicking ITER

Simulated burn control

ELM pacing, Influence of pedestal on core

Approach to nominal ITER H-mode operating point

Conventional H-Modes

Disruption induced runaway electron dynamics

Safe scenario control development for axisymmetric stability (ITER like equilibria)

Fast-particle-driven collective modes in low/reversed shear

Magnetic rotation braking, comparisons with NTV theory

Adaptive disruption mitigation; NIMROD/KPRAD modeling

Macro-Stability

Measure 4.6 GHz LH waves in core plasma

ICRF mode conversion regimes; Flow drive

ICRF/LHCD synergies

ICRF sheath physics

LHCD with compound phasing

Wave-Plasma

DEMO-like tungsten divertor

Sheath rectification, sputtering; Erosion

Deuterium retentionLy-α opacity, modeling

SOL turbulence and transport; Blob dynamics; Validation of E-M turbulence models

Plasma Boundary

Investigate portion of k-space responsible for electron energy transport

Gyrokinetic modeling of fluctuations and fluxes in ITB regimes

Nature of momentum coupling at edge

Impurity and momentum transport

Role of e- heating and LHCD on self-generated flows

Transport Science

*Progress expected in most topics (red indicates incremental funds required to speed up hardware upgrades and/or increased run time)

Highest Priority Needs for Additional Funding

• Run Time– 6 weeks in FY09/FY10– 5 weeks in FY11

• Personnel– 2 scientists, 3 engineers, 2 technicians, 2 post-docs

• Hardware– Lower Hybrid and ICRF– Poloidal field control power supply upgrades– DNB upgrade

• Diagnostics– Polarimetry (additional channels)– Divertor diagnostics– Core fluctuations

Summary National Budgets, Run-time and StaffingFY10A FY10B FY11A FY11B FY11D FY09Request IncrementGuidance Increment Decrement

Funding ($ Thousands) Research 6,700 6,700 7,400 6,850 7,650 6,180Facility Operations 13,634 14,234 15,655 14,615 16,000 13,230Capital Equipment 400 0 0 0 0 0PPPL Collaborations 3,372 3,372 3,709 3,456 3,802 2,910UTx Collaborations 340 340 440 350 450 320LANL Collaborations 100 100 110 100 110 90MDSplus 155 155 155 155 170 140International Activities 80 80 80 80 80 35Total (inc. International) 24,781 24,981 27,549 25,606 28,262 22,905Staff Levels (FTEs) Scientists & Engineers 52.1 53.0 57.4 53.8 57.5 50.2Technicians 28.5 30.3 34.3 30.3 34.3 28.3Admin/Support/Clerical/OH 18.0 18.5 20.0 18.0 20.0 16.2Professors 0.3 .3 .3 .3 .3 .3Postdocs 2.0 2.0 3.0 2.0 3.0 2.0Graduate Students 32.3 28.9 31.1 28.9 28.9 25.9Industrial Subcontractors 2.0 2.0 2.2 2.0 2.2 1.5Total 135.2 135.0 148.3 135.3 146.2 124.4

FY10A FY11D FY11A FY11B FY08Actual

FY09Request Reduced Guidance Incremental

Facility Run Schedule Research Run Weeks 15.7 10 13 6 13 18Users (Annual) Host 41 39 40 38 40 42 Non-host (US) 65 65 64 62 64 66 Non-host (foreign) 50 48 50 45 50 52Graduate students 32 29 28 26 28 28Undergraduate students 4 5 5 5 5 7Total Users 192 186 185 174 185 194Operations Staff (Annual) Host 70 67 68 65 68 70 Non-host 4 4 4 3 4 5Total 74 71 72 68 72 75

C-Mod will Continue to Make Major Progress for Fusion Science and Fusion Energy

• Flexible, Capable Facility• Excellent Tools and Diagnostics• Key Upgrades to Facility and Diagnostics

Research supported by U.S. Department of Energy, Office of Fusion Energy Sciences

Unique and Complementary Contributions to Joint (National and International) Experiments

Model Validation across Broad Range of Dimensional and Dimensionless parameters

Key Contributions to solution of challenges for ITER and Beyond