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

Conference · Mon Jan 01 00:00:00 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; TRN: 91-001913
• Resource Relation: Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

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