Large-database cross-verification and validation of tokamak transport models using baselines for comparison

被引:1
|
作者
Abbate, J. [1 ]
Fable, E. [2 ]
Grierson, B. [3 ]
Pankin, A. [1 ]
Tardini, G. [2 ]
Kolemen, E. [1 ,4 ,5 ]
机构
[1] Princeton Plasma Phys Lab, Princeton, NJ 08540 USA
[2] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[3] Gen Atom, San Diego, CA 92121 USA
[4] Princeton Univ, Dept Mech & Aerosp Engn, Princeton, NJ USA
[5] Princeton Univ, Andlinger Ctr Energy & Environm, Princeton, NJ USA
关键词
MIXED BOHM/GYRO-BOHM; ARBITRARY COLLISIONALITY; BOOTSTRAP CURRENT; SIMULATIONS; CONDUCTIVITY;
D O I
10.1063/5.0190908
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
State-of-the-art 1D transport solvers ASTRA and TRANSP are verified, then validated across a large database of semi-randomly selected, time-dependent DIII-D discharges. Various empirical models are provided as baselines to contextualize the validation figures of merit using statistical hypothesis tests. For predicting plasma temperature profiles, no statistically significant advantage is found for the ASTRA and TRANSP simulators over a baseline empirical (two-parameter) model. For predicting stored energy, a significant advantage is found for the simulators over a baseline empirical model based on confinement time scaling. Uncertainty in the results due to diagnostic and profile fitting uncertainties is approximated and determined to be insignificant due in part to the large quantity of discharges employed in the study. Advantages are discussed for validation methodologies like this one that employ (1) large databases and (2) baselines for comparison that are specific to the intended use-case of the model.
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页数:12
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