charles c. baker virtual laboratory for technology presented at the u.s. iter forum
DESCRIPTION
US ITER Technology Issues. Charles C. Baker Virtual Laboratory for Technology presented at the U.S. ITER Forum University of Maryland, College Park May 8, 2003. R. Aymar/ Fusion Engineering and Design 55 (2001). Fig. 1 Cutaway of ITER. T. Mizoguchi/Fusion Engineering and Design 55 (2001). - PowerPoint PPT PresentationTRANSCRIPT
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
Charles C. Baker
Virtual Laboratory for Technology
presented at the
U.S. ITER ForumUniversity of Maryland, College Park
May 8, 2003
US ITER Technology IssuesUS ITER Technology Issues
VLTVirtual Laboratory for TechnologyFor Fusion Energy ScienceFig. 1 Cutaway of ITER
R. Aymar/ Fusion Engineering and Design 55 (2001)
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
T. Mizoguchi/Fusion Engineering and Design 55 (2001)
Fig. 1 Central solenoid model coil (CSMC) configuration (above) and fabricated modules (below) during assembly at JAERI, Naka (JA). Another TF insert coil is fabricated by Russia and tested at JAERI.
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
H. Tsuji et al. /Fusion Engineering and Design 55 (2001)
Fig. 2 Fabrication flow of CS model coil and CS insert coil.
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
T. Mizoguchi/Fusion Engineering and Design 55 (2001)
Fig. 3 Toroidal field model coil (TFMC) configuration (above left), internal coil structure (ICS) with LCT coil (above right) and TFMC in the TOSCA Hall at FZK, Karlsruhe (EU).
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
T. Mizoguchi/Fusion Engineering and Design 55 (2001)
Fig. 5 Two half-sectors (above) of full-scale vacuum vessel sector (JA) before field joint and equatorial port (RF) after assembly at JAERI, Tokai (JA).
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
T. Mizoguchi/Fusion Engineering and Design 55 (2001)
Fig. 6 Demonstration of remote welding (US).
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
T. Mizoguchi/Fusion Engineering and Design 55 (2001)
Fig. 8 Cut-out of prototype shield blanket module for destructive examination (JA).
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
T. Mizoguchi/Fusion Engineering and Design 55 (2001)
Fig. 10 Integrated inner divertor cassette (above left) at Sandia (US), integrated outer divertor cassette (below) at EFET (EU) and high heat flux testing of divertor target by ion beam (above right) at JAERI, Naka (JA).
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
T. Mizoguchi/Fusion Engineering and Design 55 (2001)
Fig. 11 Overview of blanket test platform at JAERI, Tokai (JA). The 180o rail is shown in the right side. From right to left, the 180o support, the 90o support and the vehicle with the manipulator are attached to the rail.
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
T. Mizoguchi/Fusion Engineering and Design 55 (2001)
Fig. 13 Overview of divertor test platform at ENEA, Brasimore, (EU).
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
R&D Resources Summary and New R&D for ITER-FEAT(from TAC-16 Progress Report-R&D, June 25-27, 2000)
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
R&D Resources Summary and New R&D for ITER-FEAT(from TAC-16 Progress Report-R&D, June 25-27, 2000)
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
R&D Resources Summary and New R&D for ITER-FEAT(from TAC-16 Progress Report-R&D, June 25-27, 2000)
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
TECHNOLOGIES ARE REQUIRED TO ADVANCE SCIENCE.
Heating & Current Drive
Fueling
Magnets
Disruption Mitigation
PFC/PMI
TOOLS DEVELOPMENT NEEDED TO GET TO
•Steady-state
•Advanced Performance
•Burning Plasmas
Better gyrotrons
Better ion cyclotron launchers and control
Faster inside-launch pellets
Compact torus injection tests
Increased B-field/$
Improved innovative superconductor cable
Fast, reliable disruption detection
Fast low-Z liquid/gas injection system
Lower erosion, higher heat flux PFCs
Integrated PMI code
SCIENCE/TECHNOLOGY PARTNERSHIP
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
Magnet Technology Highlights
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
PW8, reached 24MW/m2 in EB1200
PW-8HIPped
PW-14e-beamwelded
One rod melted after 500 cycles at 20 MW/m2.
PW-8, PW-14 and PW-14b after testing in EB1200.
PW-14be-beamwelded
PFC Testing for ITER
• Development of W PFC continues to show improvement in capability and reliability (SNL)
• Mixed materials (C, Be, W) erosion studies are in progress at UCSD
• Tritium retention and removal studies in progress at SNL and INEL
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
RF Technology Highlight:The JET-EP ICRF Antenna and the High Power Prototype (HPP)
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
ECH Highlight: 1.5 MW, 110 GHz Gyrotron Development
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
Plasma Fueling Highlights:1. Massive Gas Puff for Disruption Mitigation - Mainline Tokamaks2. Pellet injector in a Suitcase - Alternative Confinement Devices3. Pellet fuelling - H-mode fuelling
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
Chamber Technology Achievements in FY02/03
MTOR allows experiments on MHD fluid flow in self-cooled liquid metals, and free-surface liquid walls.
Facilities were constructed and operated to address liquid breeder MHD in both free-surface and closed channels.
Sophisticated and complex computer code development is underway for 3-D modeling of fluid flow.
Established a temperature window in which a liquid wall can operate within an MFE reactor with a high exit coolant temperature for power conversion.
Explored advanced solid wall blanket concept with potential to improve the attractiveness of fusion power plants.
Obtained experimental results of the effective thermal properties of beryllium packed beds.
FLIHY addresses key issues and innovative techniques for enhancing heat transfer in low-conductivity fluids in closed channel flows.
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
VLTVirtual Laboratory for TechnologyFor Fusion Energy Science
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.
2m high x 1.8m wide x 3.5m long2m high x 1.8m wide x 3.5m longWeight Weight 66 tonne66 tonneSide and bottom Side and bottom 130mm thick130mm thickFront & port flange Front & port flange 200mm200mm
Equatorial port-plug concept
Port-plug with penetrations for Thomson scattering, interferometry, etc.
Designs byC. Walker (JCT)