H mode power threshold database for ITER
- 1 September 1996
- journal article
- special topic
- Published by IOP Publishing in Nuclear Fusion
- Vol. 36 (9) , 1217-1264
- https://doi.org/10.1088/0029-5515/36/9/i11
Abstract
The ITER Threshold Database, which at present comprises data from nine divertor tokamaks, is described. The main results are presented and discussed. The properties and dependences of the power threshold in individual devices are reviewed. In particular, the analysis shows a rather general linear dependence on magnetic field, but a non-monotonic density dependence that varies from device to device. Investigation of the combined database suggests that the threshold dependence Pthres approximately=0.3neBT 2.5 shows reasonable agreement with the data. This expression yields Pthres approximately=150 MW at a density of 0.5*1020 m-3 for ITER. Other expressions with weaker size dependence, and therefore lower threshold power for ITER, are also discussed. Their agreement with the present data is poorer than that of the above expression. In addition, the database is investigated by statistical discriminant analysis. The edge data included at present are described and discussed. Finally, there is a discussion of the implications of the results for ITERKeywords
This publication has 14 references indexed in Scilit:
- Experimental survey of the L-H transition conditions in the DIII-D tokamakPlasma Physics and Controlled Fusion, 1994
- First ohmic H modes in ALCATOR C-MODNuclear Fusion, 1994
- ITER H mode confinement database updateNuclear Fusion, 1994
- An emerging understanding of H-mode discharges in tokamaks*Physics of Fluids B: Plasma Physics, 1993
- Hmode of the W 7-AS stellaratorPhysical Review Letters, 1993
- Physics of the L-mode to H-mode transition in tokamaksPlasma Physics and Controlled Fusion, 1992
- Global energy confinement H-mode database for ITERNuclear Fusion, 1992
- The H-Mode of ASDEXNuclear Fusion, 1989
- Confinement physics of H-mode discharges in DIII-DPlasma Physics and Controlled Fusion, 1989
- Regime of Improved Confinement and High Beta in Neutral-Beam-Heated Divertor Discharges of the ASDEX TokamakPhysical Review Letters, 1982