The salient feature of 1989-1990 operation at JET has been the use of beryllium as a first wall material. Technical and safety aspects of JET operation with beryllium are described. The use of beryllium has substantially improved the plasma purity and as a consequence a record fusion product (nD; Ti τE) of 9x1020 m-3.keV.s has been achieved. Impurity influxes however prevent the achievement of higher plasma parameters and reaching steady state conditions. A new divertor configuration has been proposed for JET with a view to study impurity control, fuelling and exhaust, in conditions relevant for the next generation of machines. The latest design features a multi-coil configuration which gives substantive operational flexibility. A technical description of the major components of the divertor including the internal coils, the target plates the pumping and fuelling systems is given.