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

摘要

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.