alcator integrated scenarios c mod iter h-mode baseline€¦ · cmod alcator-validation of iter...

C ModAlcator

−

Integrated Scenarios

ITER H-mode BaselinePresented by:

Stephen M. Wolfe

Alcator C-Mod PAC MeetingMIT Plasma Science & Fusion CenterCambridge, MAMar 2-4, 2011

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C ModAlcator

−Definitions and Scope

By “Integrated Scenarios”, we mean research aimed at reachingattractive operating points, generally cutting across multiple sciencetopics and often involving interaction and compatibility issuesbetween different plasma processes or regions

• The ITER Q = 10 DT H-mode baseline scenario features� Positive shear, q0

<∼ 1� q95 ≈ 3, βN = 1.8, HH ∼ 1, fNI ∼ 0.25, n/nG ∼ 0.85� Edge transport barrier

� BT = 5.3T,Ip = 15MA, n̄e ≈ 1× 1020m−3

• Research effort also supports aspects of the ITER “Pre-nuclear CommissioningPhase”� Operation in H and/or He majority

� Reduced parameters (≥ 12BT , Ip)

� Alternate RF Scenarios

� Issues of H-mode access, character

Alcator C-Mod PAC Meeting Mar 2-4, 2011 smw 1

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C ModAlcator

−Research Focus and Orientation

Compared to the Topical Science areas, the H-mode IntegratedScenarios Research Program is more focussed on support of ITERconstruction and operations planning

• Respond to requirements identified by IO� Strong IO participation in program planning

� IO staff involvement in design, execution, analysis of experiments

• Participate in identification, definition, and execution of Joint Experiments andHigh Priority research activities of ITPA

• Proactively identify and address issues relevant to ITER planning and operation

• Address C-Mod issues of integration and scenario development impacting ourability to carry out ITER-related research


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C ModAlcator

−Addressing ITER H-mode Scenario issuesin C-Mod requires integration

Issues, Challenges are similar for C-Mod and ITER

• Divertor and wall materials and conditioning� High heat flux requirement

� Compatibility with low core radiation, Zeff

� Hydrogen isotope retention and recovery

• ICRF Heating� Challenging RF power density

� Compatibility with H-mode edge, high ne operation, ELMs

� Compatibility with wall conditioning requirements

• Control of pedestal parameters, edge relaxation� Variation of edge parameters (ν∗,β)

� Particle and impurity control

� ELM control


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C ModAlcator

−C-Mod H-mode Scenarios Research Topics

• Demonstration and validation of ITER reference scenarios� Ramp-up/Ramp-down phases

� Flattop “ITER demo” discharges

� Benchmarking of Simulation Models

• H-mode access and performance requirements

• Power handling, particle control, and impurity seeding

• Scenarios for ITER “Pre-nuclear phase”� Reduced field, current

� H, He majority operation

� IC Heating Scenarios

• Development and validation of Plasma Control strategies

• Plasma Material Interactions (addressed in Boundary section presentations)

• ELM and Pedestal Physics (see presentations on Transport and Pedestal Physics)


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C ModAlcator

−Validation of ITER reference startup C. Kessel

• Proposed ramp to 15 MA flattop in 80 sec

scales to C-Mod 1.35MA in 0.35 to 0.6 sec

(depending on 〈Te〉)• Full bore plasma with x-point formation at ∼ 1

4

maximum current needed to avoid overheating

ITER limiters

• ITER startup scenario requires low 0.7 < li < 1

for vertical stability; needs to conserve V-sec to

increase burn time

• Progress in 2010-11 experiments

� Perform density variations in rampup

? Examine effect on V-sec consumption, li, etc.

? Ohmic, ICRH, LHCD ramp-ups with similar

target n̄e

? Addresses PAC 2010 Recommendation

� Examine LH injection in rampup

? Validate ITER simulations which showed LH

has strongest impact in V-s and li of

IC/EC/LH

� Benchmarking models used for ITER simulations

ITER has determined that early diverting and large bore plasmas will be its baseline startup scenario

ITER is planning to divert at ~ 15 s in a 100 s Ip rampup

In order to simulate ITER-like discharges in C-Mod, the divert time has been reduced to 80-100 ms out of a 500 ms Ip rampup

Cleaner early plasma conditions compared to previous year

2008

2009

Time, s0.50.0

ITER must conserve volt-seconds in Ip rampup and control the current profile

C-Mod confirms V-s saving with ICRF heating in rampup

C-Mod indicates no change in li with ICRF heating, examining in TSC simulations

IT E R

C -Mod

ohm icICRF


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C ModAlcator

−Effect of density variation in ITER-likeOhmic ramp-up experiments C. Kessel

• Density range0.65 < n̄e < 1.8× 1020m−3

(0.08 < n/nG < 0.2)

• Low density is required forsignificant V-sec saving

• Increased Zeff at low,intermediate densitycompensates increased Te

• Delayed sawtooth onset,reduced li for lowest densitycase

• Uniform response oftemperature profile atbeginning of flattop


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C ModAlcator

−Initial results with LH injection in current rampshow savings of V-sec

• At Low density (n̄e∼5×1019m−3)400kW LH saves V-sec, relative toOH (or IC)

• li reduced by ∼ 10%

• Surface voltage drops promptly atLH turn-on

• Prad and Zeff are elevatedrelative to ohmic

• Effect reduced at higher n̄e

� Hard X-rays observed at alldensities

� Higher LH power may bebeneficial

� Possible relation to “densitylimit” effect (see LHpresentation)


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C ModAlcator

−Comparison of semi-empirical energy transportmodels in C-Mod ramp-up simulations C. Kessel

Theory-based models (e.g. GLF23) have

difficulty modeling L-mode, higher q95, ramp-

up phase

Compare semi-empirical models Coppi-Tang,

Bohm-gyroBohm,

Current Diffusive Ballooning Model (CDBM)

• BgB did reasonably well with Ohmic, but

predicted too high li with ICRF

• CT (with Cq = −3.5, Xmult = 2.75)

reasonable in ICRF, too low li in ohmic

• CDBM reasonable in ohmic, too high liand too peaked Te with ICRF

• Coppi-Tang with original settings based

on TFTR ohmic discharges had overly

peaked Te profiles and high li

None of these models appear to

sufficiently capture details of C-Mod

ramp-up experiments


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C ModAlcator

−C-Mod rampdown experiments address issues,constraints on ITER rampdown

• Start rampdown with EDAH-mode

• Inject ICRF power at varyinglevels, sustaining H-modes lateinto ramp

• Density tracks current (∼ constantn/nG) in ICRF heated H-mode

• Tpede also drops smoothly with

current

• H-mode avoids CS (OH1)over-current for sufficiently fastramp, at the expense of increasingli

ITER-like plasma rampdown experiments indicate that the density tracks Ip in ICRF

heated H-modesExamined 3 rampdown rates

Start rampdown with EDA H-mode

Inject ICRF power at varying levels

Sustaining H-modes thru rampdown phase

Requires ICRF powerHighly reproducible trajectories for li and nH-mode avoids OH overcurrent so long as Ip rampdown is fast enough

These results have already been used in ITER simulations

These results have already been used in ITER simulations


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C ModAlcator

−Scenario demonstrations: Full discharge sequence

• Demonstration of ITER-like equilibrium, 〈p〉, Te/Ti, power density� Control of operating point

� Benchmark transport, stability modeling

� Evaluate impurity, particle control

� Evaluate disruptivity, stability issues

• Exploration of variations about reference scenario

• Continue Validation of robust ramp-down, shut-down sequence

• Compatibility of core and boundaryInteraction with plasma-facing materials, including heat-flux and particle control,impurity seeding

• Demonstration of reliable, benign fault-handling and mitigation techniques


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C ModAlcator

−ITER Scenario Demonstration: IOS-1.1

• ITPA Joint Experiment IOS 1.1“ITER baseline at q=3, βN = 1.8,ne = 0.85nG (D, H, He)”� Some flexibility allowed in parameters

� Issues for C-Mod include ICRF at high density, stationary H-mode atq < 3.5, acheivable βN with available power

• Lower field option relieves some constraints� Relevant to pre-nuclear phase studies

� Experiments at half-field (2.7 T) (2010-11)

� Field overlap with other participating tokamaks, e.g. JET, providesgyro-size scaling opportunity

• Full-field C-Mod experiments at modest n/nG (2011-12)� Extension of demo experiments at higher and lower density in next

campaigns

� Target condition for seeding experiment IOS-1.2,Ramp-down validation IOS-2.2


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C ModAlcator

−Half field demonstration of access to ITER-like(IOS-1.1) parameters in EDA discharges C. Kessel

• Targeting q95 ∼ 3, βN>∼ 1.7,

κ ∼ 1.8,n/nG ∼ .85,H98 ∼ 1

• B = 2.7 T, use 2nd harmonic

H-minority ICRF heating scenario,

f ∼ 80 MHz

• Ip = 650kA operation (compares to

7.5MA in ITER at 2.7T (half-field))

� q95 = 3− 3.2

� βN<∼ 1.9

� H98 = 0.8− 0.95

� κ ∼ 1.75

• Some high βN discharges exhibit n=2,3

low frequency MHD (NTM?) or small

ELM activity, in addition to typical EDA

QC mode signature.


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C ModAlcator

−Near-term directions for C-Mod scenariovalidation work

• Continue development of half-field ITER-like discharge

• Develop and exploit full field (5.4 T) ITER-like discharge supporting ITPA JointExperiments

• Extend Ramp-up experiments with LHCD

• H-mode access and sustainment during current ramps (up and down)

• Continue evaluation and benchmarking of transport models to improve projectionsto ITER


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C ModAlcator

−H-mode access: Power Requirements for highconfinement H-modes A. Loarte(IO),J.Hughes, M.Reinke

• Motivation: ITER QDT = 10 H-mode Scenario

requires

� H98 ∼ 1 with Pnet/Pth ∼ 1.1− 1.4

(Pth = 0.49n0.72e B0.8S0.94)

� qdiv <10MWm−2 → Prad/Ploss ∼ 0.8

Po−div/Ploss < 0.2

• Experimental goals:

� Examine pedestal and confinement

characteristics as function of margin above

threshold power

� Evaluate margin above Pth required to reach

H∼1 in stationary conditions

� Role of core/edge radiation on power

requirement

H98∼1 achievable for sufficientPnet=Ploss−Prad−core

Low Po−div achievable with low Z seeding

Page 752nd APS Division of Plasma Physics Meeting , Chicago, Illinois, USA

� Impurity Seeding � Power scans of Pin & Pnet by scanning PICRH and impurity species/amount (N2, Ne, Ar)

�H98 ~ 1 achievable if Pnet is

high enough

�Low Po-div for lower Z seeding

Overview of Alcator C-Mod Experiments (II)

Low Z seeding � added benefits on

ICRH operation

� Fewer trips allowing high PICRH

� No increase of core Mo

S. Wukitch �� TP9.89 (Thursday am)

0

1

2

3

4

5

0.0

0.2

0.4

0.6

0.8

1.0

0.0 0.3 0.6 0.9 1.2 1.5

0.0

0.2

0.4

0.6

0.8

1.0

[MW

]

PRAD,CORE

Pin

H98

Time [sec]

[MW

]

Power to outer

divertorAr

Ne

N2


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C ModAlcator

−Power requirements for high confinementH-modes (cont)

• High confinement (H98y2 ∼ 1) achieved

for high Pnet

• Seeding allows variation of Ploss,

Prad,total

• Confinement directly correlated with Tped

consistent with picture based on core

profile stiffness

• Pnet/Pth is good ordering parameter

(roughly equivalent to net power / particle )

• Pedestal cooling at low Pnetmore

pronounced with Ar than Ne or N2, as

expected from radiation profiles

• Low Z Impurity seeding results in higher

performance H-modes

reduces incidence of high Z impurity

injections and also reduces ICRF trips

• H98,Pnet/Pth in ITER target range

obtained with low Z seeding


� Plasma confinement directly correlated with pedestal temperature �

Universal correlation (Seeded & Unseeded H-modes)

� Higher H98 for low Z seeding associated with higher ne for same Tped

Pedestal & Confinement : Seeded H-modes

H9

8

Te,95 (eV)Te,95 (eV)

ne,9

5 (

10

20m

-3)

unseeded

Ne

Ar

N2

unseeded

Ne

Ar

N2


Power Flow & Confinement : Seeded H-modes

� Impurity seeding allows scanning both Pin and Prad in controlled

fashion � same Pnet with different Pin and Prad,core (� Prad,total/Ploss)

� High confinement achieved for high Pnet and no overfuelling of SOL

unseeded

Ne

Ar

N2

H9

8

Pnet / Pth

ITER


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C ModAlcator

−Low divertor heat flux with low-Z seeding meetsITER spec

• Partially detached divertorconditions achieved with Ne andN2 seeding and H98∼1

• Peak q‖ reduced by over a factor 5from unseeded caseExceeds ITER requirement

• Outer divertor temperaturereduced from 1000◦C to ∼ 250◦Cwith Pnet>2MW

• H98,Po−div in ITER target rangeobtained with low-Z seeding

52nd APS Division of Plasma Physics Meeting , Chicago, Illinois, USA

� Pnet ≥ Pth (or high enough Tped) required to maintain H98 ~ 1 � ☺ ITER� If Pnet ≥ Pth � high Prad,div, low qdiv (& divertor detachment) can be achieved

with H98 = 1 by low Z seeding in C-Mod � ☺ITER� ITER QDT = 10 requirements (H98 = 1 @ Pnet/Pth ~ 1 & Po-div/Ploss < 0.2) have

been achieved by impurity seeding in H-modes ☺� optimization of

impurity mix (Ar vs. Ne, N2) may be required for highest Prad/Zeff in ITER � �

Summary and Conclusions

unseeded

Ne

Ar

N2

H98

Pnet / Pth

ITER

N2 seeded

Ne seeded

unseeded

Ar seeded

0 0.1

1.0

0.8

0.6

1.2

0.2 0.3 0.4

Po-divertor / Ploss

HIT

ER

-98

(y,2

)

ITER


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C ModAlcator

−Control of divertor power balance using radiation seeding (IOS-1.2)

• C-Mod experiments feature ITER-like divertor

power density, geometry, neutral opacity, . . .

• Extensive pedestal and divertor diagnostics

• Build on seeding results from H-mode access

experiment (2009-11)

• Optimization of Seeding, Radiative divertor control

(2010-11)

� Extend toward more ITER-like core plasma

(lower q95, . . . )

� Evaluate at higher density, investigate effect of

high edge ne

� Localization of impurity puff to minimize core

contamination, maximize divertor protection

� Dynamic comparison of recycling (Ne) and

non-recycling (N2) seed

• Develop feedback control for optimized divertor

protection, core performance (2011-12)

• Apply to ITER-like conditions 2012-13Page 1

Alcator C-mod Ideas Forum 2010 10th-12th January 2011

Optimisation of radiative H-modes & determination of mechanism for confinement deterioration at high <ne> (I)

� C-Mod has demonstrated that plasma confinement is correlated with Pnet/Pth and that

high Prad/Ploss can be achieved with H98 ~ 1 with low Z seeding

� Experiments performed at medium <ne> and midplane impurity puffing � large

average Zeff

� Discharges with high ne,edge following boronization showed poor confinement despite

large Pnet/Ploss

New experiments :

� Optimisation to achieve highest Prad/Ploss with H98 ≥ 1 & lowest Zeff to demonstrate ITER requirements (core Zeff)

� Determine mechanisms of confinement deterioration at high <ne>

Reinke PSI’10, Hughes IAEA’10, Loarte APS’10

3

• Compare the required amount of gas (N2 and Ne) required for a fiducial discharge from a number of locations  5 toroidally-spaced NINJA capillaries in the floor of

the divertor  Midplane puffing  Up H-port (B-port as well?)  Design and install new gas tube into divertor from

midplane port • Develop feedback control of impurity seeding.

Feedback on  X-point bolometer chords (ratio and absolute value)  Thermoelectric currents

Experiments are needed to optimize the seeding feed loaction

NINJA capillaries

New divertor gas feed

• Experiments  Before break compare H-port to B-side in terms of divertor vs core radiation (5 shots)  After break

 Standard fiducial 0.8-1.0 MA EDA: vary gas injection location (1 run)  Use optimal location to develop feedback (1 run)


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C ModAlcator

−ITER “Pre-Nuclear” Phase (first 2-3 years)

• No deuterium operationmajority H (or He), minority He3

• Heating, CD sources undercommissioning� Ptot

<∼ 73MW (NBI, EC, IC)

� 40 < fICRF < 55MHz,PICRF ≤ 20MW

� fECRF = 170GHz,PECRF ≤ 20MW

• BT between half and full field

• CFC divertor (decision ontransition to W tbd)

Page 1Alcator C-mod Ideas Forum 2010 10th-12th January 2011

Access & exit from H-mode and H-mode characteristics versus heating deposition profile (I)

� ITER heating systems (33 MW-NNBI, 20 MW–ICRH, 20 MW-ECRH) �

conditions on development of scenarios from low Bt (2.65T) to high Bt (5.3T)

�Main issues : Shine-through for NBI, heating schemes (ICRH) and deposition location (ECRH)

� ECRH launchers designed to optimise use of ECRH in ITER (including heating of plasmas off-axis) � influence of off-axis heating on H-mode

access and performance needs to be assessed

0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5

BT(T)

0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

ne(1020m−3)

EC EC

IC

H minority in He

IC

3He minority

in H and He

H0

NB shinethrough

(armour, 4MW/m2

)

in H

in 4

He

q.95

= 3

ne = 0.85 nGW

ρICRH < 0.15

ρECRH < 0.5

ρECRH < 0.9

ITER Heating availability in H and He plasmas

0

5

10

15

I p(MA)

0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.50

5

10

15

BT(T)

I p(MA)

0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5

0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

ne(1020m−3)

EC EC

IC

H minority

IC3He minority

(D and DT)

2 ωcT

(DT)

D0

NB shinethrough

(armour, 4MW/m2

)

q.95

= 3

ne = 0.85 nGW

ρICRH < 0.15

ρECRH < 0.5

ρECRH < 0.9

ITER Heating availability in D and DT plasmas

Issues:• Access to H-mode

• Ability to validate ELM mitigation technique

• Alternate RF scenarios


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C ModAlcator

−Access to ELMy H-mode in helium majorityplasmas

C-Mod experiment comparing He toD majority plasma in sameconfiguration as used for EPED-1validation study run on previous day

• Operation with majority He (some

residual D)

• Robust access to ELMy discharges at

similar power levels as in D

• Pedestal parameters also comparable to

deuterium

• H98 ∼ 1 obtained with T pede ∼ 800eV

• Results obtained over range of density,

current, power for comparison with

comparables in D, model validation

• Results favorable for prospects of

accessing ELMy H-mode in ITER

pre-nuclear phase (with sufficient power)

0 0.5 1 1.5 2-1-0.8

-0.6

-0.4

-0.2

0 Ip (MA)

0 0.5 1 1.5 20

0.5

1

1.5

2nebar(1e20/m3)

0 0.5 1 1.5 20

1

2

3

ICRF power (MW)

0 0.5 1 1.5 20

0.5

1

1.5

2

2.5 HeII monitor

0 0.5 1 1.5 20

5

10

15

20Electron betap(95) (%)

0 0.5 1 1.5 200.2

0.4

0.6

0.8

1

1.2 H ITER98y2


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C ModAlcator

−Near-term C-Mod Activities in support ofpre-nuclear phase

• Investigate L-H and H-L threshold� Species dependence of transition and confinement He (and H ?) majority

� Evaluate dependence on X-point height, equilibrium details(Pedestal/Transport Group)

� Evaluate dependence on heating profile (relevant to fixed frequency EC)(Pedestal/Transport Group)

• Characterize He majority H-modes in ITER-like configurations

• Assess relevant ICRF scenarios� He3 minority in H majority plasmas (ICRF Group)

� Consider H majority scenarios


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C ModAlcator

−Development of plasma operational controlmethods

• C-Mod & ITER PFsets have similararrangement and(multi-parameter)functionality

• Large vessel andstructure currents,especially duringstartup, ramp-down

• MIMO shape control with few actuators, minimal null space, operation nearcurrent, voltage, stress limits

• RF-based actuators for heating, non-inductive current drive

• Negligible central particle, momentum sources


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C ModAlcator

−Development and testing of plasma controlalgorithms

• Testing of plasma control strategies in relevant scenarios

� Effects of sensor noise, transient events

� Effects of currents in passive structures on control

and reconstructions

� Benchmarking of simulation codes

• Development and testing of machine protection

algorithms

� Identification of and response to sensor, actuator

faults

� Response to proximity to actuator limits

adaptive transfer to “safe shutdown sequence” or

real-time pulse “rescheduling”

� Real-time identification of proximity to plasma

instability boundaries

ITER Requires Large Gaps for Transient ControlM d li f H d t L d T iti t Q 10 ith 15 MAModeling of an H-mode to L-mode Transition at Q=10 with 15 MA

Radial inward displacement can be ≥ 10cm contact with the inner wall

Duration of inner wall contact depends on the central solenoid saturation state

Peak engineering heat loads of ~40MW/m2 Be tiles would melt in ~ 0.3 s!

PCS must maintain large enough gaps or trigger the disruption mitigation system

3J A Snipes, 2011 C-Mod Ideas Forum, MIT 10 - 12 January 2011

Need experiments & modeling to demonstrate & extrapolate control of transients

ITER Requires Large Gaps for Transient ControlM d li f H d t L d T iti t Q 10 ith 15 MAModeling of an H-mode to L-mode Transition at Q=10 with 15 MA

Radial inward displacement can be ≥ 10cm contact with the inner wall

Duration of inner wall contact depends on the central solenoid saturation state

Peak engineering heat loads of ~40MW/m2 Be tiles would melt in ~ 0.3 s!

PCS must maintain large enough gaps or trigger the disruption mitigation system

3J A Snipes, 2011 C-Mod Ideas Forum, MIT 10 - 12 January 2011

Need experiments & modeling to demonstrate & extrapolate control of transients


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C ModAlcator

−Development and testing of plasma controlalgorithms: Safe Shutdown Sequence

Example: Runaway electron discharges sometimes

encountered when running low density

• Current carried by fast (MeV) electron tail

• Large hard X-ray flux can damage sensitive

electronics

• Runaway beam can damage internal

components, blamed for some melt damage

on guard limiters

• Generally undesirable condition

Jump-ahead routine implements “soft landing”

• Senses Hard X-ray levels above threshold

during pre-set interval

• Jumps into ramp-down sequence by advancing

synchronous time counter

• In routine use during 2010-11 Experimental

Campaign

� No false positives

� 31 Successful discharge terminations

Runaway Sensing

0.0

0.5

1.0

Ip (MA)

0.0

0.6

1.2

ne (1020 m-3)

0

2

4

Hard X-rays (AU)

0 1 2t (sec)

0.0

0.5

1.0

0 1 2

Ip Program (MA)

X-ray threshold

Jump-to time

Xjump Gate 106

0307

003

106

0307

004

StandardSoft rampdown


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C ModAlcator

−Burn Control simulation experiments with ICRH1

Study evolution and stationary states of plasma with power dependent on plasmaparameters (IOS-6.3: Control of experimentally simulated burning state)

• Use ICRF minority heating tomimic centrally peaked fastion heating

• Control (part of)PICRF ∝ n2f(T ) or RDD tosimulate burn

• Apply feedback to try tomaintain constant burn poweragainst perturbations such asELMs, sawteeth, MHD,density excursions, etc

• Experiments in 2012-13

1suggested by P. Politzer (GA)


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C ModAlcator

−C-Mod H-mode Scenarios Research Program

• Program elements paced by

� ITER priorities

� C-Mod facility capabilities – Actuators, Diagnostics, Control system, Internals

• 2010-11 (since last PAC meeting):

� Approximately 9.5 run days so far (including FY10-11)

� Scenario demonstrations: Ramp-up, ramp-down; half-field scenarios

� H-mode access: Power requirements for high confinement

� Extension of impurity seeding studies

� Pre-nuclear phase: ELM characteristics in He majority plasmas

� Testing of pedestal model (see Pedestal presentation)

• 2011-12: New rotated 4-strap ICRF antenna, Improved seeding capability,

� Optimization of radiative H-modes

� ITER demos (IOS-1.1) at full field

� Extend impurity seeding (IOS-1.2) studies, develop feedback control of divertor radiation

� Evaluation of transient control requirements

� H-mode access and characteristics during current ramps

� Current rampup scenarios with LHCD

• 2012-13: Second New 4-strap ICRF antenna and automatic matching system, Additional LH launcher,DPCS enhancements

� Burn control studies

� Continue impurity seeding and power handling studies

� Development and testing of advanced plasma control/fault sensing algorithms


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C ModAlcator

−C-Mod Research on Integrated Scenarios forITER H-mode Baseline

• H-mode baseline research program addresses cross-cutting physics andtechnology issues

• Exploits ITER-relevant C-Mod parameters and tools

• Addresses High-priority ITER Research Needs

• Strongly coupled to ITPA tasks, Joint Experiments

• Many additional ITER-related experiments in Topical Science Groupsand Alternate Scenarios


alcator integrated scenarios c mod iter h-mode baseline€¦ · cmod alcator-validation of iter...

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