ARIES Compact Stellarator Reactor - PowerPoint PPT Presentation

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ARIES Compact Stellarator Reactor

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Title: ARIES Compact Stellarator Reactor


1
NCSX Construction Progress and Research Plans
Hutch Neilson for the NCSX Team Princeton Plasma
Physics Laboratory Oak Ridge National Laboratory
IEEE/NPSS Symposium on Fusion
Engineering Knoxville, TNSeptember 27, 2005
2
Topics
  • NCSX Mission
  • Design, Key Requirements.
  • Construction Progress.
  • Research Plans.
  • Theme Realizing complex geometry requirements in
    the finished product.

3
Compact Stellarator Benefits to Magnetic Fusion
  • Stellarators solve critical problems.
  • Steady state without current drive.
  • No disruptions stable without feedback control
    or rotation drive.
  • Unique flexibility to resolve 3D plasma physics
    issues.
  • Compact Stellarators have additional
  • benefits
  • Magnetic quasi-symmetry. In NCSX
  • Quasi-axisymmetric configuration with effective
    ripple lt1.5.
  • Low flow damping, tokamak-like orbits? enhanced
    confinement
  • Makes full use of tokamak advances, allowing
    rapid and economical development.
  • Lower aspect ratio than typical stellarators.
  • 4.4 in NCSX vs. 11 in W7-X.

NCSX has low effective ripple.
4
Stellarator Benefits Are Due to its 3D Geometry
  • Stellarators create confining magnetic
    configuration with magnets alone.
  • Robust mode of operation, simple control.
  • Compact stellarators take advantage of 3D shaping
    flexibility to design for additional attractive
    properties.
  • Compactness, good confinement, high-? stability,
    etc.

Engineering challenge geometry and tight
tolerances in magnets and associated
structures. NCSX Project objective engineering
realization of a system to test the physics
benefits of compact stellarators.
Plasma and Coil Design for the National Compact
Stellarator Experiment (NCSX)
5
NCSX Mission Compact Stellarator Attractiveness
  • Acquire the physics data needed to assess the
    attractiveness of
  • compact stellarators advance understanding of 3D
    fusion science.
  • Understand
  • Beta limits and limiting mechanisms.
  • Effect of 3D magnetic fields on disruptions
  • Reduction of neoclassical transport by QA design.
  • Confinement scaling reduction of anomalous
    transport.
  • Equilibrium islands and neoclassical tearing-mode
    stabilization.
  • Power and particle exhaust compatibility w/good
    core performance.
  • Alfvénic mode stability in reversed shear compact
    stellarator.
  • Demonstrate
  • Conditions for high-beta, disruption-free
    operation.

6
NCSX Physics Design
  • Plasma / coil configuration was optimized to
    realize target physics properties.

Plasma Cross Sections
  • Physics Properties
  • 3 periods, low R/?a? (4.4).
  • Quasi-axisymmetric w/ low ripple.
  • Stable at ?4.1 to specific MHD instabilities.
  • Reverse shear q-profile.
  • 25 of transform from bootstrap.
  • Good magnetic surfaces at high ?.
  • Constrained by engineering feasibility metrics
  • coil-coil spacing
  • min. bend radius
  • tangential NBI access
  • coil-plasma spacing.

7
NCSX Coils Flexibility to Vary Physics Properties
rotational transform
Shear controlled by varying plasma shape ?4.2,
full current, fixed profiles.
  • Magnet system has 4 coil sets
  • Modular, TF, PF, trim.

normalized radius
  • Also
  • Can externally control iota.
  • Can increase ripple by 10x, preserving
    stability.
  • Can lower theoretical b-limit to 1.
  • Can cover wide operating space in ? (to at least
    6), IP, profile shapes.

8
Modular Coil Design Meets Physics Requirements
  • 18 modular coils (3 shapes)
  • Robust structural shell design minimizes
    deflections.
  • Toroidal and poloidal breaks inhibit eddy
    currents.
  • Lead arrangement minimizes field errors.

Modular Coil Structure
Winding form (one per coil).
Winding current centers follow physics-optimized
design to 1.5 mm (0.1) accuracy.
9
Vacuum Vessel Design Meets Physics Requirements
  • Physics Requirements
  • High-vacuum environment for good plasma
    performance.
  • Sufficient interior space for plasma, boundary
    layer, and PFCs.
  • Access for heating and diagnostic viewing.
  • Low field errors.
  • Engineering constraint be able to
  • slide the modular coils over the
  • vacuum vessel (w/ ports removed).
  • Design
  • Vacuum boundary inside coils, as far from plasma
    surface as possible.
  • Shell geometry similar to plasmas. Tolerance
    3 mm.
  • About 100 ports, filling all available openings
    in surrounding magnets.
  • Inconel material.
  • Bakeable to 350 C.

10
NCSX Can Produce Required Plasma Conditions.
Stellarator Major radius 1.4 m Magnetic Field
(B) _at_ 0.2 s pulse 2.0 T _at_ 1.7 s pulse 1.2
T Plasma current 350 kA. Plasma Heating
(planned) NBI 6 MW (tangential) ICH 6 MW
(high-field launch) ECH 3 MW
  • High ? (4) Plasma Scenario
  • B 1.2 T, P 6 MW
  • (?E  2.9 ? ISS95 L-mode assumed)
  • ne 6 ? 1019 m-3
  • Ti(0)  1.8 keV
  • ?i  0.25

11
Construction
  • Key engineering challenge accurate realization
    of the geometries
  • required in the magnets, vacuum vessel, and
    associated structures.
  • NCSX Project Strategy
  • Manufacturing RD Develop critical processes
    prior to construction.
  • Modular coil winding forms / structures.
  • Modular coil windings.
  • Vacuum vessel.
  • System engineering Manage flow-down of
    requirements from physics specification to
    finished product.

12
Vacuum Vessel Manufacturing RD
  • Scoping studies during conceptual design
  • Manufacturing analyses by 5 industrial suppliers.
  • Examined process issues.
  • Shell segmentation to minimize welding.
  • Weld fixturing to minimize distortion.
  • Port attachment.
  • Prototyping and supplier qualification during
  • preliminary design.
  • Two competing suppliers, cost-type contracts.
  • Developed manufacturing and QA plans for NCSX
    specs.
  • Built 20-degree prototype sectors.
  • Submitted sound proposals for production order.
  • Production Contract awarded Sept., 2004
  • Major Tool and Machine, Inc.

Prototype Vacuum Vessel Sector
13
Modular Coil Manufacturing RD
  • Scoping studies during conceptual design
  • Multiple suppliers examined process issues.
  • Alloy and casting options to minimize
    deformation.
  • Identified lowest-risk acquisition strategy
  • Winding forms cast and machined by industry.
  • Coil fabrication by Laboratory staff.
  • Winding form prototyping and supplier
  • qualification during preliminary design.
  • Two competing suppliers, cost-type contracts.
  • Developed manufacturing and QA plans for NCSX
    specs.
  • Built prototype castings.
  • Submitted sound proposals for production order.
  • Production Contract awarded Oct., 2004
  • Energy Industries of Ohio, Inc.

Casting being poured.
Casting ready to be machined.
14
Major Component Manufacture is Proceeding Well
Modular Coil Winding Form being machined
Vacuum Vessel sector fabrication
Manufacturing RD eliminated major technical
uncertainties for component production.
15
Modular Coil Winding RD
  • Flexible conductor handling / winding.
  • Keystoning and insulation tests
  • Vacuum pressure impregnation
  • Process development
  • Material properties
  • Mechanical tests (tension, compression, flexure,
    fatigue)
  • Thermal tests (CTE, conductivity)
  • Electrical resistance
  • Twisted Racetrack Coil(integrated demonstration)
  • Developed efficient process for accurate coil
    manufacture.
  • Improved the design for manufacturability.
  • Tested at operating temperature, current, and
    pulse length.

VPI mold development.
Twisted RacetrackCoil
16
Coil Fabrication is Ready to Start
Winding and Conductor Payout Fixtures
Modular Coil Mfg. Facility
17
System Engineering Ensures Requirements Flow Down
to Finished Product.
Dimensional Control Metrology Strategies,
equipment, and procedures for realizing required
1.5 mm winding accuracy. ? Coil fabrication
(0.5 mm) Field period assembly (0.5 mm) Final
assembly (0.5 mm)
Analysis Dynamic CAD modeling verifies that coils
can be installed over vacuum vessel.
18
Construction Will Be Completed in 2009.
  • MCWFs delivered in FY06-07.
  • Coil winding in FY06-07.
  • Sub-assembly activities start when VV sectors
    arrive in FY06.
  • Final assembly testing FY08-09.
  • First Plasma July, 2009.

19
Research Program Will Address Physics Issues for
Compact Stellarator Attractiveness.
20
Summary
  • Research on NCSX will test the expected physics
    benefits of compact stellarators.
  • Steady state, no disruptions, compact,
    tokamak-like physics.
  • Realization of required 3D component and assembly
    geometries is the main engineering challenge.
  • Progress in NCSX construction project indicates
    no obstacles to engineering realization of
    compact stellarators.
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