charles c. baker virtual laboratory for technology presented at the u.s. iter forum

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)


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.


H. Tsuji et al. /Fusion Engineering and Design 55 (2001)

Fig. 2 Fabrication flow of CS model coil and CS insert coil.



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).



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).



Fig. 6 Demonstration of remote welding (US).



Fig. 8 Cut-out of prototype shield blanket module for destructive examination (JA).



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).



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.



Fig. 13 Overview of divertor test platform at ENEA, Brasimore, (EU).


R&D Resources Summary and New R&D for ITER-FEAT(from TAC-16 Progress Report-R&D, June 25-27, 2000)


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


Magnet Technology Highlights


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


RF Technology Highlight:The JET-EP ICRF Antenna and the High Power Prototype (HPP)


ECH Highlight: 1.5 MW, 110 GHz Gyrotron Development


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


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.


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)

charles c. baker virtual laboratory for technology presented at the u.s. iter forum

Documents

mizoguchifusion engineering

new rd

progress reportrd

rd resources summary

aymar fusion engineering

lct coil

tokai ja

naka ja