Comparison of ITER performance predicted by semi-empirical and theory-based transport models

被引:42
作者
Mukhovatov, V
Shimomura, Y
Polevoi, A
Shimada, M
Sugihara, M
Bateman, G
Cordey, JG
Kardaun, O
Pereverzev, G
Voitsekhovich, I
Weiland, J
Zolotukhin, O
Chudnovskiy, A
Kritz, AH
Kukushkin, A
Onjun, T
Pankin, A
Perkins, FW
机构
[1] ITER Int Team, Naka, Ibaraki 3110193, Japan
[2] Lehigh Univ, Bethlehem, PA 18015 USA
[3] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon, Oxon, England
[4] Max Planck Inst Plasma Phys, EURATOM Assoc, IPP, Garching, Germany
[5] Univ Aix Marseille 1, Equipe Turbulence Plasma, Marseille, France
[6] Chalmers Univ Technol, S-41296 Gothenburg, Sweden
[7] EURATOM, NFR Assoc, Gothenburg, Sweden
[8] ITER Int Team, Garching, Germany
[9] Russian Res Ctr, Kurchatov Inst, Nucl Fus Inst, Moscow, Russia
[10] Gen Atom Co, San Diego, CA 92186 USA
关键词
D O I
10.1088/0029-5515/43/9/318
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
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, P-aux = 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.
引用
收藏
页码:942 / 948
页数:7
相关论文
共 37 条
[11]  
KARDAUN OJW, 2002, IPPIR2002511 M PLANC
[12]   On estimating the epistemic probability of realizing Q=Pfus/Paux larger than a specified lower bound in ITER [J].
Kardaun, OJWF .
NUCLEAR FUSION, 2002, 42 (07) :841-852
[13]   Interval estimation of global H-mode energy confinement in ITER [J].
Kardaun, OJWF .
PLASMA PHYSICS AND CONTROLLED FUSION, 1999, 41 (04) :429-469
[14]   QUANTITATIVE PREDICTIONS OF TOKAMAK ENERGY CONFINEMENT FROM FIRST-PRINCIPLES SIMULATIONS WITH KINETIC EFFECTS [J].
KOTSCHENREUTHER, M ;
DORLAND, W ;
BEER, MA ;
HAMMETT, GW .
PHYSICS OF PLASMAS, 1995, 2 (06) :2381-2389
[15]  
KRITZ AH, 2002, P 29 EPS C CONTR F B, V26
[16]   The spectral profile of the HeI singlet line (667.82 nm) emitted from the divertor region of JT-60U [J].
Kubo, H ;
Takenaga, H ;
Kumagai, A ;
Higashijima, S ;
Suzuki, S ;
Sugie, T ;
Sakasai, A ;
Itami, K .
PLASMA PHYSICS AND CONTROLLED FUSION, 1999, 41 (06) :747-757
[17]   Divertor modelling and extrapolation to reactor conditions [J].
Kukushkin, AS ;
Pacher, HD .
PLASMA PHYSICS AND CONTROLLED FUSION, 2002, 44 (06) :931-943
[18]   High density operation in H mode discharges by inboard launch pellet refuelling [J].
Lang, PT ;
Gafert, J ;
Gruber, O ;
Kaufmann, M ;
Lorenz, A ;
Maraschek, M ;
Mertens, V ;
Neuhauser, J ;
Salzmann, H .
NUCLEAR FUSION, 2000, 40 (02) :245-260
[19]   Electromagnetic drift wave simulations of high performance discharges at JET [J].
Nordman, H ;
Strand, P ;
Weiland, J ;
Christiansen, JP .
NUCLEAR FUSION, 1999, 39 (09) :1157-1163
[20]   Models for the pedestal temperature at the edge of H-mode tokamak plasmas [J].
Onjun, T ;
Bateman, G ;
Kritz, AH ;
Hammett, G .
PHYSICS OF PLASMAS, 2002, 9 (12) :5018-5030