Predictive tests of ITG-based models of tokamak heat transport on ITER-database discharges
Three gyro-Bohm transport models are applied to the L-mode discharges of the international thermonuclear experimental reactor (ITER) profile database for predictive tests of plasma confinement. All three models are based on the ion temperature gradient (ITG) driven turbulence but emphasize different aspects of the resulting turbulent transport. It is found that the model using the long wave-length component of the turbulence for the radial correlation length yields predictions with the lowest overall residual error for the given database. Extrapolations for the performance of ITER are given for the models.
Bibliographic Reference: Report: EUR-CEA-FC-1630 EN (1998) 32pp.
Availability: Available from Association Euratom-CEA, CEN Cadarache, 13108 Saint-Paul-lez-Durance (FR)
Record Number: 199810708 / Last updated on: 1998-06-08
Original language: en
Available languages: en