Association EURATOM-Max-Planck-Institut fur Plasmaphysik, D-85748 Garching, GermanyIntroductionThe application of resonant magnetic perturbation fields is a promising technique to controltransient heat loads due to large type-I edge localised modes (ELM) in tokamaks. Previous ex-periments have shown that n > 4 (n is the toroidal mode number) magnetic field perturbationwere able to trigger small ELMs during otherwise ELM-free H-mode phases on JFT-2M [1].Magnetic perturbations with n =1 and m =4−5 were able to increase the repetition frequencyof type-III ELMs in COMPASS-D [2]. Recent results from DIII-D usingn =3 magnetic per-turbation fields have shown that type-I ELMs can be completely suppressed in collisional andcollisionless plasmas [3]. All of these experiments have in common that the applied coil sys-tems were built into the vacuum vessel and had only a small separation to the plasma. Fornext-step fusion devices, such as ITER, it may not be feasible to use internal coils due to techni-cal constraints. ELM mitigation using magnetic perturbation fields generated with external coilsystems (which are further away from the plasma than coils build into the vessel) and havinglow toroidal mode numbers (which have less radial decay of field strength than higher n modes)needs to be explored for ITER-relevant plasma conditions with high triangularity and high beta.This paper summarizes recent experiments on the JET tokamak where it has been shownthat type-I edge localised modes can be controlled by an externally generated perturbation fieldusing a set of four error field correction coils (EFCC) [4] which allows one to apply perturbationfields with toroidal mode numbers n =1 or n =2.