First wall and divertor performance and lifetime analysis for the US ITER design

Conference · Mon Jan 01 04:00:00 EST 1990

OSTI ID:6224647

Mattas, R F

The performance of the ITER first wall and divertor have been analyzed using the Fusion Lifetime Prediction (FLIP) code. The code is a one-dimensional finite difference code which calculates the changes in properties, stress, strain, and temperature overtime for plate structures. The results indicate that the first wall should be able to accommodate up to {approximately}0.6 MW/m{sup 2} heat flux for the reference operating conditions. At much higher levels, fatigue and cracking are predicted to lead to rapid failure. The loss of ductility in irradiated austenitic stainless steel at low temperatures is a concern which may limit operating life. The results of the divertor analysis show that a bare, 2 mm thick plate of Nb-1Zr or TZM can accommodate fluxes of 15--20 MW/m{sup 2} for the ITER conditions. Duplex structures composed of 2 mm of tungsten on 2 mm of Nb-1Zr or TZM are limited to 8--10 MW/m{sup 2}. 3 refs., 8 figs., 3 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6224647
• Report Number(s): CONF-901007-56; ON: DE91006661
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700202 -- Fusion Power Plant Technology-- Magnet Coils & Fields
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
AUSTENITIC STEELS
CLOSED PLASMA DEVICES
CRACKS
DESIGN
DIVERTORS
FATIGUE
FINITE DIFFERENCE METHOD
FIRST WALL
HEAT FLUX
IRON ALLOYS
IRON BASE ALLOYS
ITER TOKAMAK
ITERATIVE METHODS
MECHANICAL PROPERTIES
NUMERICAL SOLUTION
PERFORMANCE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
SERVICE LIFE
SPECIFICATIONS
STEELS
TEMPERATURE DISTRIBUTION
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES