5313

4983

كارشناسي ارشد

فيزيك

اصفهان: دانشگاه صنعتي اصفهان، دانشكده فيزيك

1388

ده،87ص.:مصور،جدول،نمودار

ص.ع.به فارسي و انگليسي

اكبر پروازيان

ظفرالله كلانتري

13/4/89

احمد شيراني

فيزيك

ID4983

به فارسي و انگليسي: قابل رويت در نسخه ديجيتالي

۵ Lower Hybrid Current Drive In NSTX Tokamak Mona Niroozad m niroozad@ph iut ac ir Date of Submission 2010 01 10 Department of physics Isfahan University of Technology Isfahan 84156 83111 Iran Degree M Sc Language Farsi Supervisor Akbar Parvazian parvazin@cc iut ac ir Abstract It is usually recognized that a considerable amount of heating power additional to the ohmic heating will be required to reach ignition in a tokamak reactor To this purpose we use the method of the injection of wave In the large tokamaks poloidal magnetic field is ignorable versus toroidal magnetic field Since toroidal magnetic field is very large we can use cyclotron waves to heat plasma But in small tokamaks toroidal magnetic field is very weak and this method is not efficient Therefore in small tokamaks people use current drive methods to confine plasma Lower hybrid wave have proven excellent at driving plasma current Steady state current drive is important for tokamak fusion reactors A large effort has been devoted to produce Steady state current drive and reduce product cost Spherical tokamaks have low ratio aspect and can confine a higher plasma pressure for a given magnetic field strength Since in the small tokamaks the magnitude of the poloidal magnetic field and toroidal magnetic field are in the same order We can use poloidal magnetic field for plasma confinement The National Spherical Torus Experiment NSTX is an innovative device based on the Spherical Tokamak concept that is investigated in this thesis This tokamak itself can produce inductive current and reduce inductive current production costs In this thesis the results of LSC for NSTX and TFTR tokamak is discussed This results indicate higher efficiency of NSTX tokamak and express the fact that we can access to a higher external power with redusing the cost and construct time Keywords NSTX Tokamak Lower Hybrid Waves Current Drive Quasilinear Diffusion Coefficient Quasilinear Power

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