TY - JOUR
T1 - Comparison of ITER performance predicted by semi-empirical and theory-based transport models
AU - Mukhovatov, V.
AU - Shimomura, Y.
AU - Polevoi, A.
AU - Shimada, M.
AU - Sugihara, M.
AU - Bateman, G.
AU - Cordey, J. G.
AU - Kardaun, O.
AU - Pereverzev, G.
AU - Voitsekhovich, I.
AU - Weiland, J.
AU - Zolotukhin, O.
AU - Chudnovskiy, A.
AU - Kritz, A. H.
AU - Kukushkin, A.
AU - Onjun, T.
AU - Pankin, A.
AU - Perkins, F. W.
PY - 2003/9
Y1 - 2003/9
N2 - The values of Q = (fusion power)/(auxiliary heating power) predicted for ITER by three different methods are compared. The first method utilizes an empirical confinement-time scaling and prescribed radial profiles of transport coefficients; the second approach extrapolates from specially designed ITER similarity experiments, and the third approach is based on partly theory-based transport models. The energy confinement time given by the ITERH-98(y, 2) scaling for an inductive scenario with a plasma current of 15 MA and a plasma density 15% below the Greenwald density is 3.7 s with one estimated technical standard deviation of ±14%. This translates, in the first approach, for levels of helium removal, and impurity concentration, that, albeit rather stringent, are expected to be attainable, into an interval for Q of [6-15] at the auxiliary heating power, Paux = 40 MW, and [6-30] at the minimum heating power satisfying a good confinement ELMy H-mode. All theoretical transport-model calculations have been performed for the plasma core only, whereas the pedestal temperatures were taken as estimated from empirical scalings. Predictions of similarity experiments from JET and of theory-based transport models that we have considered - Weiland, MMM, and IFS/PPPL - overlap with the prediction using the empirical confinement-time scaling within its estimated margin of uncertainty.
AB - The values of Q = (fusion power)/(auxiliary heating power) predicted for ITER by three different methods are compared. The first method utilizes an empirical confinement-time scaling and prescribed radial profiles of transport coefficients; the second approach extrapolates from specially designed ITER similarity experiments, and the third approach is based on partly theory-based transport models. The energy confinement time given by the ITERH-98(y, 2) scaling for an inductive scenario with a plasma current of 15 MA and a plasma density 15% below the Greenwald density is 3.7 s with one estimated technical standard deviation of ±14%. This translates, in the first approach, for levels of helium removal, and impurity concentration, that, albeit rather stringent, are expected to be attainable, into an interval for Q of [6-15] at the auxiliary heating power, Paux = 40 MW, and [6-30] at the minimum heating power satisfying a good confinement ELMy H-mode. All theoretical transport-model calculations have been performed for the plasma core only, whereas the pedestal temperatures were taken as estimated from empirical scalings. Predictions of similarity experiments from JET and of theory-based transport models that we have considered - Weiland, MMM, and IFS/PPPL - overlap with the prediction using the empirical confinement-time scaling within its estimated margin of uncertainty.
UR - https://www.scopus.com/pages/publications/0141842723
UR - https://www.scopus.com/inward/citedby.url?scp=0141842723&partnerID=8YFLogxK
U2 - 10.1088/0029-5515/43/9/318
DO - 10.1088/0029-5515/43/9/318
M3 - Article
AN - SCOPUS:0141842723
SN - 0029-5515
VL - 43
SP - 942
EP - 948
JO - Nuclear Fusion
JF - Nuclear Fusion
IS - 9
ER -