Technology Challenges for Diagnostics for MFE Measurement and Control PowerPoint PPT Presentation

presentation player overlay
1 / 15
About This Presentation
Transcript and Presenter's Notes

Title: Technology Challenges for Diagnostics for MFE Measurement and Control


1
Technology Challenges for Diagnostics for MFE
(Measurement and Control)
  • K. M. Young (PPPL)
  • FESAC Priorities Sub-Group
  • May 21, 2004

2
ITER provides Unique Technical Challenges for
Diagnostics
Measurement requirements demand performance
capability for present-day machines
alpha-particle measurement, operation in
radiation environment, presence of blankets,
reliability, calibration maintenance, control
data for machine protection. Significant
engineering design issues.
Port-plug with penetrations for Thomson
scattering, interferometry, etc.
  • 2m high x 1.8m wide x 3.5m long
  • Weight 66 tonne
  • Side and bottom 130mm thick
  • Front port flange 200mm

Designs by C. Walker (JCT)
Equatorial port-plug concept
3
Technology Issues for Diagnostics
  • Long-pulse (steady-state) device issues
  • Maintenance of alignment, calibration,
    reliability,
  • High temperature/neutral particle impact on
    windows (seals),
  • Coating of optical components (metallic mirrors,
    windows).
  • Cooling of active components (e.g. shutters,
    detectors),
  • Design of supporting structures,
  • Development of new detectors/sources (some
    examples)
  • High temperature solid-state X-ray detectors,
  • Compact solid-state magnetic sensors,
  • Detectors for Alternate Concept Devices,
  • Stable cw intermediate-power microwave sources,
  • IR fiberoptics.
  • Neutral Beams for Active Spectroscopy,
  • Other neutral-particle sources??
  • Criteria for the input to plasma control.

4
Additional Technology Issues for Diagnostics for
BPXs
  • Neutron environment significantly raises the
    challenge
  • Integration of components and shielding
    structures with remote handling (already an issue
    on JET),
  • Radiation effects on components,
  • Real-time changes in properties,
  • Noise background,
  • Survival,
  • Neutronics calculations for viability, shielding,
  • Operation of mechanical hardware (e.g. shutters,
    actuators, location sensors),
  • Detectors for the environment
  • Bolometers,
  • High-temperature sensors for escaping a-particles.

5
Alignment, Calibration, Reliability
  • With long port necks and plasma very close to
    limiting surfaces, diagnostics must maintain
    precise alignment independent of large structural
    movements near them.
  • Techniques for checking on calibration during
    long pulses must be developed
  • Present-day diagnostics have operated with
    extraordinary reliability after long shakedown
    but a new level is required
  • e.g. Thomson scattering laser (and windows,
    mirrors) will have gt1x107 pulses (gt1x104 in one
    discharge).

6
Living with the Environment inside the Vacuum
Vessel
  • Qualification of materials that can be used in
    vacuo at high temperature (and radiation?)
  • Vacuum windows to withstand neutral-particle
    bombardment, high temperature excursions (plus
    hot walls) will probably have to be developed,
  • Deposition of coatings and dust on windows,
    mirrors, sensitive detectors must be understood
    and be quantifiable. Can it be removed in vacuo?
  • Cooling techniques (mounting or active cooling)
    have to be developed.
  • Components must be designed for ease of
    replacement (possibly by remote handling).

7
Intense Neutral Beams are Critical for Diagnostics
  • Measurements dependent on Neutral Beams
  • Emission from plasma neutrals
  • Ion temperature CXRS, X-ray Crystal, Neutrons
  • Poloidal rotation CXRS, X-ray Crystal
  • Toroidal rotation CXRS, X-ray Crystal
  • Core impurities CXRS (low-Z), X-ray Crystal
    (high-Z)
  • Core helium-ash CXRS
  • Thermalizing Alphas CXRS
  • Emission from beam neutrals
  • Current density MSE, polarimetry, Zeeman
    (edge/Li-beam)
  • Turbulence Beam Emission Spectroscopy,
    Reflectometry
  • CXRS, MSE and BES provide local measurements.
    Requirements on spatial and temporal resolution
    for physics and control of advanced tokamaks may
    be met.

8
The Development Issue for a DNB
Approximate numbers
Compression of beam size by factor 90 for ITER
DNB (using HB source) is extreme (not including
divergence). Current density extrapolation is
huge.
9
Operational Issues for the Neutral Beams
  • For ITER Heating Beam
  • Primary function to heat and drive
    current/rotation,
  • Wide range of energies planned (400 - 1000 keV),
  • Variable angle capability (?),
  • Control diagnostic (MSE) should not be dependent
    on a system being controlled.
  • For ITER Diagnostic Beam
  • Same beam hardware is planned as for heating
    beam, even though ve beam may be better at 100
    keV.
  • For ve beam no optimization considered to
    maximize signal strength versus beam energy,
    including beam neutralization.
  • For IDNB
  • Major development effort required
  • Frequency and reproducibility of source,
  • Divergence and neutralization are key issues not
    yet addressed.
  • Note for NCSX a lower energy, lower power beam
    is required (STTR?)

10
Integration of Systems to provide Plasma Control
  • AT tokamak performance will be controlled using
    (noisy) plasma profile information.
  • BPXs must operate close to the b-limit based on
    plasma parameter profiles.
  • Amelioration must be triggered early,
  • Too far short of limit gives low-Q,
  • Over limit causes hardware damage.
  • Active MHD control will be required.
  • Raw diagnostic data must be integrated with
  • software and responding systems to allow for best
  • plasma performance for extended periods.

11
Integration of Diagnostics with Shielding and the
Impact of Radiation Streaming in Penetrations
  • Radiation streaming is a critical concern for
    FIRE. Impacts
  • Coil insulation and local diagnostic components
    in real time,
  • activation levels in the hall.
  • Pre-conceptual designs done of penetrations of
    two ports for first streaming calculations.
  • First calculations of average fluxes at the
    back-plate (150 MW pulse, 1.1 m plug)
  • No penetrations 1.0x107 n/cm2/s,
  • With 100 mm dia. 1.3x1011 n/cm2/s,
  • straight penetration,
  • With 100 mm dia. 2.0x109 n/cm2/s,
  • 4-bend penetration.
  • Activation levels acceptable with 3.4m port neck
    filled by shielding and additional component
    shielding.

1.1 m shield
  • No full engineering design of the port
    configurations or remote handling interface has
    been done for FIRE.

12
Electrical Impact and Concerns of Radiation
Radiation-induced Conductivity (RIC) in Ceramics
  • Insulators for Diagnostics
  • RIC Concern for FIRE Radiation dose at first
    wall 8 x 103 Gy/sec, significantly higher than
    for ITER magnetic diagnostics.
  • Radiation-induced emf (RIEMF) and
    radiation-mediated thermoelectric potential
    (RMTP) in MI cable may be most severe issue (work
    in progess in EU JA).
  • Rapid time behavior in studies of RIEMF?
  • Nuclear heating (200C in 20 s. in FIRE).
  • Damage to electronic components.
  • FIRE (and ITER) still require
  • intensive RD on radiation effects.

Conductivity too high
______________
X
13
Optical Impacts of Radiation
Recent Russian measurements on ITER- preferred
fibers.
Lost-a diagnostic on TFTR suffered from
luminescence in fiberoptic outside vacuum vessel.
TFTR shot at 5MW (5x10-2 MW/m2 at first wall).
Dose at front end of shielded fiber estimated
30 Gy/s.
700 Gy/s, gtgt ITER/FIRE flux outside port.
Prompt luminescence (and absorption) in fibers
and windows are critical issues in quantitative
diagnostic measurement.
14
Other Considerations for the Radiation Environment
  • Development of an International Data Base of
    diagnostic materials and components
  • ITPA Activity.
  • Neutronics modeling facility to rapidly validate
    shielding designs and diagnostic integration.
  • Capability to carry out validation tests on
    materials and components
  • Selection of parts to be used,
  • Pre-operational testing for BPX.
  • Facility for prototyping and testing of major
    components,
  • Development program of moveable mechanisms,
    actuators, motion-sensors for use in the
    environment (incorporate cooling?)
  • Capability for assessing tritium-contamination
    impact.

15
Concluding Comments
  • The engineering of diagnostics is amongst the
    most challenging tasks for future fusion devices
  • Provide data throughout all the plasma
    performance,
  • Large physical scale,
  • Control and machine protection,
  • Reliable operation.
  • Many of the technology issues are common to many
    diagnostics.
  • Extremely costly to duplicate efforts,
  • Extensive testing capabilities.
  • An urgent, aggressive RD program in diagnostics
    should be started (revived?).
  • A central capability (real or virtual in
    location) could provide a necessary and desirable
    resource.
  • My emphasis has been on tokamaks - others could
    better define work for other devices.
Write a Comment
User Comments (0)
About PowerShow.com