TY - JOUR
T1 - Multi-machine transport analysis of hybrid discharges from the ITPA profile database
AU - Imbeaux, F.
AU - Artaud, J. F.
AU - Kinsey, J.
AU - Tala, T. J.J.
AU - Bourdelle, C.
AU - Fujita, T.
AU - Greenfield, C.
AU - Joffrin, E.
AU - Na, Y. S.
AU - Parail, V. V.
AU - Sakamoto, Y.
AU - Sips, A. C.C.
AU - Voitsekovitch, I.
PY - 2005/12/1
Y1 - 2005/12/1
N2 - Current diffusion, heat transport modelling, and linear gyrokinetic stability analysis have been carried out on a set of seven hybrid discharges from AUG, DIII-D, JET and JT-60U, in order to gain better understanding of the physics underlying this promising candidate scenario for ITER. Within this dataset, the GLF23 model has a higher accuracy than the Weiland model in predicting the temperature profiles in the region 0.3 < ρ < 0.8. The core heat transport appears to be similar between hybrid discharges and standard H-modes, and also among hybrid discharges with very different H factors. Projections to ITER show that Q ≤ 10 can be obtained with the hybrid scenario using an alternative scaling without β degradation. However, additional off-axis current drive and current profile control might be needed for the ITER hybrid scenario, in order to achieve its full potential for high βN on extended duration.
AB - Current diffusion, heat transport modelling, and linear gyrokinetic stability analysis have been carried out on a set of seven hybrid discharges from AUG, DIII-D, JET and JT-60U, in order to gain better understanding of the physics underlying this promising candidate scenario for ITER. Within this dataset, the GLF23 model has a higher accuracy than the Weiland model in predicting the temperature profiles in the region 0.3 < ρ < 0.8. The core heat transport appears to be similar between hybrid discharges and standard H-modes, and also among hybrid discharges with very different H factors. Projections to ITER show that Q ≤ 10 can be obtained with the hybrid scenario using an alternative scaling without β degradation. However, additional off-axis current drive and current profile control might be needed for the ITER hybrid scenario, in order to achieve its full potential for high βN on extended duration.
UR - http://www.scopus.com/inward/record.url?scp=27744479167&partnerID=8YFLogxK
U2 - 10.1088/0741-3335/47/12B/S14
DO - 10.1088/0741-3335/47/12B/S14
M3 - Article
AN - SCOPUS:27744479167
SN - 0741-3335
VL - 47
SP - B179-B194
JO - Plasma Physics and Controlled Fusion
JF - Plasma Physics and Controlled Fusion
IS - 12 B
ER -