The design of resistive copper toroidal field (TF) coils is described for use in a nearterm tokamak fusion device (FED-R). A design requirement on the TF coils is that they contain readily demountable joints to facilitate replacement of components inside the bore of the coil. The coils are fabricated from rectangular window frame plates with 1-m-radius fillets in the inside corners. Each coil contains 17 turns — fabricated from CDA-110 copper plate segments 6.1 em thick. Because of high radiation fluence, a ceramic turn-to-turn insulator is used. The cooling system is sized to accommodate the combined heat loading that results from resistive power dissipation and nuclear heating.