US ITER Technology Issues Charles C. Bakersites.apam.columbia.edu/fusion/Presentations_Papers/C_Baker_Oral.… · PW-8 HIPped PW-14 e-beam welded One rod melted after 500 cycles at

VLTVirtual Laboratory for Technology

For 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


For 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 outerdivertor cassette (below) at EFET (EU) and high heat flux testing of divertor target byion 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

DisruptionMitigation

PFC/PMI

TOOLS DEVELOPMENT NEEDED TO GET TO

•Steady-state

•AdvancedPerformance

•BurningPlasmas

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 after500 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 PFCcontinues to showimprovement in capabilityand reliability (SNL)

• Mixed materials (C, Be,W) erosion studies are inprogress at UCSD

• Tritium retention andremoval studies inprogress 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 allowsexperiments on MHDfluid flow in self-cooledliquid metals, and free-surface liquid walls.

wFacilities were constructed andoperated to address liquid breederMHD in both free-surface and closedchannels.

wSophisticated and complex computercode development is underway for 3-Dmodeling of fluid flow.

wEstablished a temperature window inwhich a liquid wall can operate withinan MFE reactor with a high exit coolanttemperature for power conversion.

wExplored advanced solid wall blanketconcept with potential to improve theattractiveness of fusion power plants.

wObtained experimental results of theeffective thermal properties ofberyllium packed beds.

FLIHY addresses key issues and innovativetechniques for enhancing heat transfer in low-conductivity fluids in closed channel flows.





ITER provides Unique Technical Challenges for Diagnostics

• Measurement requirements demandperformance 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 6666 tonne tonneSide and bottom Side and bottom 130mm thick130mm thickFront & port flange Front & port flange 200mm200mm

Equatorial port-plug concept

Port-plug with penetrationsfor Thomson scattering,interferometry, etc.

Designs byC. Walker (JCT)

Documents

US ITER Technology Issues Charles C. Bakersites.apam.columbia.edu/fusion/Presentations_Papers/C_Baker_Oral.… · PW-8 HIPped PW-14 e-beam welded One rod melted after 500 cycles at