%0 Journal Article %@holdercode {isadg {BR SPINPE} ibi 8JMKD3MGPCW/3DT298S} %@nexthigherunit 8JMKD3MGPCW/3ET2RFS %@archivingpolicy denypublisher denyfinaldraft12 %@resumeid 8JMKD3MGP5W/3C9JHQT %@resumeid 8JMKD3MGP5W/3C9JHB4 %@usergroup administrator %@usergroup vinicius %3 andrade-self.pdf %X A self-consistent equilibrium calculation, valid for arbitrary aspect ratio tokamaks, is obtained through a direct variational technique that reduces the equilibrium solution, in general obtained from the 2D GradShafranov equation, to a 1Dproblem in the radial flux coordinate Ï. The plasma current profile is supposed to have contributions of the diamagnetic, PfirschSchlNuter and the neoclassical ohmic and bootstrap currents. An iterative procedure is introduced into our code until the flux surface averaged toroidal current density JT, converges to within a specified tolerance for a given pressure profile and prescribed boundary conditions. The convergence criterion is applied between the JT profile used to calculate the equilibrium through the variational procedure and the one that results from the equilibrium and given by the sum of all current components. The ohmic contribution is calculated from the neoclassical conductivity and from the self-consistently determined loop voltage in order to give the prescribed value of the total plasma current. The bootstrap current is estimated through the full matrix HirshmanSigmar model with the viscosity coefficients as proposed by Shaing, which are valid in all plasma collisionality regimes and arbitrary aspect ratios. The results of the self-consistent calculation are presented for the low aspect ratio tokamak Experimento Tokamak EsfLerico. A comparison among different models for the bootstrap current estimate is also performed and their possible limitations to the self-consistent calculation is analysed. %N 12 %T Self-consistent equilibrium calculation through a direct variational technique in tokamak plasmas %@secondarytype PRE PI %K Tokamak devices, Self consistente fields, Equilibrium. %@group LAP-INPE-MCT-BR %@group LAP-INPE-MCT-BR %@secondarykey INPE-13752-PRE/8941 %@copyholder SID/SCD %@issn 0741-3335 %2 sid.inpe.br/mtc-m16@80/2006/05.29.12.37.11 %@affiliation Instituto Nacional de Pesquisas Espaciais (INPE) %@affiliation Instituto Nacional de Pesquisas Espaciais (INPE) %@affiliation Universidade Estadual Paulista (UNESP) %@project Plasma de fusão. Fusão termonuclear controlada %B Plasma Physics and Controlled Fusion %P 1269-1289 %4 sid.inpe.br/mtc-m16@80/2006/05.29.12.37 %D 2000 %@documentstage not transferred %V 42 %A Andrade, Maria Celia Ramos de, %A Ludwig, Gerson Otto, %A Camargo, S. J., %@dissemination WEBSCI; PORTALCAPES. %@area FISPLASMA