Studies of resonant magnetic perturbations (RMP) have been an active topic in the tokamak research. The RMP technique involves the use of magnetic perturbations generated by external coils installed on a tokamak device. The resonant interaction between the plasma and RMP has favorable effects on magnetohydrodynamic (MHD) stability and other plasma parameters in tokamaks. The RMP experiments are carried out in the Saskatchewan Torus-Modified (STOR-M) tokamak using (l = 2, n = 1) helical coils carrying a static current pulse. The effect of RMP on the (m = 2, n = 1) magnetic islands is examined during ohmic discharges with high MHD activities. The amplitude and frequency of (2, 1) Mirnov fluctuations are significantly reduced after application of RMP. A phase of improved plasma confinement, characterized by a reduction in the H_alpha emission level and an increase in the soft x-ray (SXR) emission, is induced after application of RMP. It is also observed using the ion Doppler spectroscopy (IDS) that RMP can strongly affect the plasma rotation in STOR-M. It is found that during the RMP pulse, the toroidal velocity of C_III impurities (located at the plasma edge) increases in the co-current direction. However, the toroidal velocities of O_V and C_VI impurities (located near the plasma core) change direction from counter-current to co-current. The reduction of the toroidal flow velocity is accompanied by a reduction of the MHD frequency. It is also found that radial profiles of ion saturation current and floating potential in the edge region can be modified by RMP. An increase in the pedestal plasma density and a more negative electric field are observed at the plasma edge region during the RMP pulse. An internal probe array is assembled and installed in STOR-M to study the RMP penetration and the plasma response to RMP.

The protection of plasma facing components from heat and particle overloads is paramount to ensure the operability and desired lifetime of magnetic fusion devices. The possibility of using external 3D magnetic perturbations to improve the steady-state heat exhaust in diverted tokamaks has been studied in this thesis. This approach involves producing a controlled stochastic region in the plasma edge without significantly affecting the core of the plasma. Using field line tracing and 3D advection-diffusion heat transport models, the resulting magnetic and heat flux footprints on the divertor have been analyzed. An optimized configuration has been obtained, which reveals the potential of this approach for considerably reducing the peak heat load on the divertor. / Att skydda plasmakomponenter mot höga värmeflöden och snabba partiklar är av största vikt föratt säkerställa funktionsduglighet och önskad livslängd för en magnetisk fusionsreaktor. Möjlighetenatt använda externa 3D-magnetiska störningar för förbättrad statisk värmeavledningeni tokamaker med magnetiska avledare har studerats i denna avhandling. Tillvägagångssättetinnebär att man producerar en kontrollerad stokastisk region i plasmakanten utan att väsentligtpåverka plasmakärnan. Med hjälp av fältlinjespårning och 3D-modellering av värmetransportsom en advektions-diffusionsprocess har de resulterande magnetiska fotspåren och värmeflödetpå avledaren analyserats. En optimerad konfiguration har erhållits, vilket visar potentialen i dettatillvägagångssätt för att avsevärt minska den maximala värmebelastningen på avledaren.