Abstract
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.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 942-948 |
| Number of pages | 7 |
| Journal | Nuclear Fusion |
| Volume | 43 |
| Issue number | 9 |
| DOIs | |
| State | Published - Sep 2003 |
| Externally published | Yes |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Condensed Matter Physics
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