# Presentation: 947462

## NSTX Facility/Diagnostics/Budget Update and Plans for FY 06 - 08

**Masa Ono**
**NSTX Program Advisory Committee Meeting**
**(PAC-19)**
**February 22- 24, 2006**

***College W&M***
***Colorado Sch Mines***
***Columbia U***
***Comp-X***
***General Atomics***
***INEL***
***Johns Hopkins U***
***LANL***
***LLNL***
***Lodestar***
***MIT***
***Nova Photonics***
***New York U***
***Old Dominion U***
***ORNL***
***PPPL***
***PSI***
***Princeton U***
***SNL***
***Think Tank, Inc.***
***UC Davis***
***UC Irvine***
***UCLA***
***UCSD***
***U Colorado***
***U Maryland***
***U Rochester***
***U Washington***
***U Wisconsin***

***Culham Sci Ctr***
***U St. Andrews***
***York U***
***Chubu U***
***Fukui U***
***Hiroshima U***
***Hyogo U***
***Kyoto U***
***Kyushu U***
***Kyushu Tokai U***
***NIFS***
***Niigata U***
***U Tokyo***
***JAEA***
***Hebrew U***
***Ioffe Inst***
***RRC Kurchatov Inst***
***TRINITI***
***KBSI***
***KAIST***
***ENEA, Frascati***
***CEA, Cadarache***
***IPP, J******ü******lich***
***IPP, Garching***
***ASCR, Czech Rep***
***U Quebec***

## NSTX Facility and Diagnostic Capabilities

**NSTX Facility and Diagnostic Capabilities**

- 2

_**Device Parameters**_
- R = 85 cm
- a = 65 cm
-  = 1.7 - 2.7
-  = 0.3 - 0.8
- BT = 5.5 kG
- TF (3.5 kG)~ 3 sec  	~ 6 skin
- Ip = 1.5 MA
- Vp = 14 m3
- Ep ~ 430 kJ
- PNBI = 7.4 MW
- PHHFW = 6 MW
- 350°C bakeout
- Passive Plates
- RWM Coils
- ICHI ~ 400 kA
- 60 cm dia. ports
- Wide tang. access

_**Major Diagnostic Systems**_
**Confinement Studies**
- Magnetics for equilibrium reconstruction
- Diamagnetic flux measurement
- _Multi-pulse Thomson scattering (30 ch)_
- _CHERS: T__i__(R) and V____(r) (51 ch)_
- _Neutal particle analyzer (2D scanning)_
- _FIReTIP interferometer (119mm, 6 ch)_
- Density Interferometer (1 mm, 1ch)
- Visible bremsstrahlung radiometer (1 ch)
- _Midplane tangential bolometer array_
- X-ray crystal spectrometer: Ti(0), Te(0)
- _MSE-CIF (8ch)_
**MHD/Fluctuation/Waves**
- High-n and high-frequency Mirnov arrays
- Ultra-soft x-ray arrays – tomography (4)
- _Fast X-ray tangential camera (2____s_)
- Wave reflectometers
- _FIReTIP polarimeter (6 ch, 600 kHz)_
- _Tangential microwave scattering_
- Electron Bernstein wave radiometer
- Fast lost-ion probe (energy/pitch resolving)
- Fast neutron measurement
- Locked-mode detectors
- RWM sensors (n = 1, 2, and 3)
**Edge/divertor studies**
- Reciprocating Langmuir probe
- _Gas-puff Imaging (2____sec)_
- Fixed Langmuir probes (24)
- _Edge Rotation Diagnostics (T__i__, V____, V__pol__)_
- 1-D CCD H cameras (divertor, midplane)
- 2-D divertor fast visible camera
- Divertor bolometer (4 ch)
- IR cameras (30Hz) (3)
- Tile temperature thermocouple array
- Scrape-off layer reflectometer
- Edge neutral pressure gauges
**Plasma Monitoring**
- _Fast visible cameras_
- Visible survey spectrometer
- VUV survey spectrometer
- X-ray transmission grating spectrometer
- Fission chamber neutron measurement
- Visible filterscopes
- Wall coupon analysis
- X-ray crystal spectrometer (astrophysics)

**In red - collaboration**
_**Underlined - tangential access**_

## FY 05 NSTX Plasma Operations Completed Successfully

- FY2005 Joule milestone: 17 run weeks
**Achieved: 18 run weeks producing 2221 plasmas.**
- All facility and diagnostic milestones completed on or ahead of schedule.
- Excellent safety record in 2005.
- Maintaining our tradition and goal!
- New Research Capabilities introduced in FY 05 yielded exciting results:
- New PF 1A divertor coils for strong shape control -  ~ 2.7,  ~ 0.8;
- Error Field / Resistive Wall Mode (EF/RWM) coils powered by Switching Power Amplifier for plasma rotation and stability control;
- 8 channel Motional Stark Effect (MSE) diagnostic for the first current profile measurement in high beta plasmas;
- 30 ch MPTS for detailed profile particularly in the pedestal region;
- 1.5 kV CHI capacitor bank and direct gas/ECH feed into injector for an efficient current generation with closed flux surfaces;
- Tangential high-k scattering system for electron transport study;
- Movable glow probe for improved particle control/boronization.
- Toroidal field coil joints operated very reliably at 4.5 kG.

**FY 05 NSTX Plasma Operations Completed Successfully**

## New Research Capabilities for FY 06 Run

**FY2006 Joule milestone: 11 run weeks**
- Plasma operations to resume in Feb. 2006 and end in May.
- New Research Capabilities implemented in FY 06
- Lithium Evaporator for improved particle recycling control for high performance long pulse discharges (March);
- Feedback capability for EF/RWM coils powered by Switching Power Amplifier to improve and extend high performance plasmas March);
- 12ch for MSE for improved current profile diagnostics particularly in the outer region;
- 2.0 kV operation of CHI capacitor bank to extend the high current generation efficiency closed flux surface formation (April);
- Bay G modification to enable remotely moveable dual EBW emission measurements covering extended frequency range 8 - 40 GHz (March);
- TF qualified to 5.5 kG;
- TF pulse length can be extended by ~20% if needed.

**New Research Capabilities for FY 06 Run**

## MHD

- FY 06

- FY 07

- FY 08

**12 **

**10 **

**8**

**10**

**11 **

**MHD**

- EF/RWM Feedback (Columbia)

- PCS Processor Upgrade (GA)

- Fast X-ray Camera (PSI)

- _Capabilities and Plan_
- • EF/RWB coils powered by SPAs operated well in pre-programmed mode in FY 05
- • Feedback control software written, compiled, and tested in simulation mode.
- • Ready to test feedback control early in FY 06 run.
- • PCS Processor Upgrade provide faster feedback control x 3-10.

**ITER**

- Control Coils

- Conducting
- _x0017_Walls

- ITER plasma shape

- ITER VV Profile

**NSTX**

- NSTX Well Positioned for Cutting Edge EF/RWM Research

- Fast Muli-Color-Te(r)(0.1ms, JHU)

## Active RWM control research on NSTX to test the basic theoretical models needed for ITER and beyond

- Growth

- rate

- [

- 1/s

- ]

- Active RWM control research on NSTX to test the basic theoretical models needed for ITER and beyond

- B (arb)

**RWM eigenfunction strongly ballooning**
**at high ********, low-A ******** outboard coils effective**

**Like ITER RWM control system****, ****NSTX feedback system has mid-plane coils and nearby **(blanket-like)** passive plates**** **

*** ******(DCON – LANL)***

**Feedback stabilize   RWM at C******** =  68% **
**when ************ << ************-crit**

***Testing resonant***
***and non-resonant ***
***braking with coils to***
***reduce/control rotation***

***VALEN***
***(Columbia Univ******.)***

***Active feedback coil***

***Passive***
***stabilizing***
***plate***

***Vacuum***
***vessel***

******N ****= 5.1****                      ****6.3****        ****6.9**
**  ****C******** = 0.0****                               ****0.68****           ****1.0**
**            ****C******** ******** (********N ****− ********N****nowall****) / (********N****wall ****− ********N****nowall****)**

**1.0**

***RWM ************ vs. ************N****** with rotation = 0***

***Sensors***

## Transport and Turbulence

- FY 06

- FY 07

- FY 08

**12 **

**10 **

**8**

**10**

**11 **

- - Base

- - Increment

- MPTS 30 ch

-  High k Scattering (UCD)

- Interim P-CHERS

- MSE/CIF 12 ch

- Full P-CHERS

- 3rd MPTS Laser

- P-CHERS

**• ****Unique** up/down** **symmetric ports along NB for optimal view
- • Transport barrier physics
- • Low aspect ratio accentuates the physics of poloidal rotational viscosity

- MSE

- High-k Scattering

- Unprecedented spatial resolution at high k

- New Channels

- MSE/CIF 16 ch (Nova)

- UCD

- Nova Photonics

- Multi-Color-Te(r)(JHU))

- Full P-CHERS

-  Decision Pt

-  Next-step Fluctn diag DP

-  Corr. Reflect. (UCLA)

## Boundary

- FY 06

- FY 07

- FY 08

**12 **

**10 **

**8**

**10**

**11 **

- Decision Pt

- - Base

- - Increment

- Lithium Evaporator

- Core Fueling DP

- Adv. Particle Exhaust DP

- Lithium Pellets

- Li evaporation rate ~ 100 mg/min
- Compare to a few mg / Li pellet

- _Achieve low particle recycling regime_
- • ~30 mg of lithium from pellets reduced recycling in FY 05
- • Utilize lithium evaporator with much higher deposition rate in FY 06
- • After FY 06 run, assess needs for:
- core fueling such as pellets or CT injector,
- further particle control system such as additional lithium evaporator, liquid lithium tray, or cryo-divertor-panel.

- Fast IR Camera (ORNL)

- Pellet Injector (ORNL)

- Divertor Dignostics (ORNL)

- 2nd Li Evap

- Extend high-performance discharges

## Waves and Energetic Particles

- Current and Pressure Profile Control for Advanced Regimes

- FY 06

- FY 07

- FY 08

**12 **

**10 **

**8**

**10**

**11 **

- Decision Pt

- - Base

- - Increment

- 1 MW EBW System

- Complete FDR
- Begin Site Prep

- Decision Point

- Complete Site Prep
- Antenna Design

- EBW

- Symmetric HHFW Feeds

- Edge Wave Reflectometer (ORNL)

- Dual EBW Radiometer (8-40GHz, ORNL)

- HHFW

- Energetic Particles

- Fast Lost Particle (JAEA)

- D-Alpha (UCI)

*New fast lost ion probe data can be used to benchmark ORBIT simulations of the energetic particle loss during MHD **(JAEA)*

- FIReTIP (0.5 MHz UCD)

- Core Reflectometer (UCLA)

- FIReTIP (2.5 MHz UCD)

- Core Wave Reflectometer (UCLA)

## Solenoid-Free Start-Up

- FY 06

- FY 07

- FY 08

**12 **

**10 **

**8**

**10**

**11 **

- - Base

- - Increment

- CHI

-  Dynamo edge probe (UCSD)

- 2 kV CHI Bank Capability

- Improved pre-ionization

- PF-only Start-up

- CHI
- In 2005, CHI bank operated at 1.5 kV, achieved very high current multiplication of ~60,closed flux surface plasma after decay of injector current
- For 2006, CHI bank being upgraded for 2 kV operation to extend toward higher current

- PF-only Start-up - favorable field scaling
- Needs for high power pre-ioinization identified
- CHI, CT-Injection and/or Plasama Gun (PEGASUS) may provide efficient pre-ionization
- Iron core concept allows new possibility

- PEGASUS: Ip = 26 kA > ITF=12 kA

## Opportunities to extend NSTX device performance

- FY 06

- FY 07

- FY 08

**12 **

**10 **

**8**

**10**

**11 **

- _FY 2005_
- TF pulse extended to 1.5 sec from 1 sec at 4.5 kG due to excellent joint resistance
- _FY 2006_
- TF Joints already tested up to 5.5 kG
- _FY 2006 - 2007_
- Extend TF pulse length as needed, extend toward 2 sec at 4.5 kG.
- take credit for TF cooling during pulse
- increase cooling water flow rate
- _FY 2008_
- • New  OH coil with potential for I2t and more flux.

## NSTX Budget Summary ($M)

- • 11 and 12 run week cases in FY 06 and 07 include minimal upgrades.
- • Incremental budget allows more optimum facility utilization and the 1 MW EBW system construction and other high priority upgrades.

## Facility, Diagnostic and Budget Summary

- 18 run weeks with all milestones completed on or ahead of schedule
- Facility upgrades: New PF 1A coils; EF/RWM coils powered by 3 ch. SPA; 1.5 kV CHI with improved ECH/gas; Movable GDC probe
- Diagnostic upgrades; High-k Scattering, 30 ch. MPTS, 8 ch. MSE-CIF, Edge Reflectometer, EBW Radiometer (18-40 GHz), Fast-sFLIP
- Planning for exciting FY06 run with new capabilities:
- 11 run weeks to start in February, end in May with June as contingency
- Facility upgrades: Lithium Evaporator (LITER), EF/RWM coils feedback, 2 kV CHI
- Diagnostic upgrades: 12 ch. MSE-CIF, Dual remotely-steered radiometer (8 - 40 GHz) for EBW emission, Dynamo probe for CHI, 1ms Multi-color-Te(r),
- New capabilities planned to support FY 07 - 08 plan:
- Facility upgrades: 2nd Lithium Evaporator (LITER), PCS Processor Upgrade
- Diagnostic upgrades: 16 ch. MSE-CIF, P-CHERS, D-Alpha detector, 2.5 MHz FIReTIP, 100 s Multi-ColorTe(r),Fast IR Camera

- Incremental budget allows NSTX to contribute significantly more to Burning Plasma Physics, AT Plasma Science, and Configuration Optimization