[en] A hybrid blanket for a reversed-field pinch (RFP) reactor is presented for breeding ²³³U from thorium. This study focuses on the shellblanket design and assumes a plasma like that used by Culham Laboratory (CL) in its designs. The ²³³U bred helps the important neutron economy and allows the tritium breeding ratio to be 0.96 at beginning of life for a mean of 1.06 for a 9 MW . yrm² burnup. A thick conducting shell is assumed for discharge stability and field reversal. This need for a good conductor requires that only pure copper or aluminum or alloys thereof be used. Two designs were investigated, one with a pure copper first wallshell, the other with an aluminum alloy. In these designs 3.4% of the thorium is converted to ²³³U. In both designs the low metallurgic temperature limit means the large amount of power deposited on and in the shell is not attractive thermodynamically. The resulting large temperature differences in the shell cause high mechanical stresses. The design as it stands is not feasible from the point of view of radiation damage to materials