Fusion Science and Technology / Volume 4 / Number 2P2 / September 1983 / Pages 603-608
Fusion System Studies / dx.doi.org/10.13182/FST83-A22928
A relatively high temperature superheated steam cycle was designed to be compatible with a D-D tokamak blanket to help identify some of the benefits of using the D-D fuel .cycle. Since less tritium leaves the plasma in a D-D reactor than in a D-T reactor and tritium is not produced in the D-D reactor blanket, it may be acceptable for steam generated in the first wall and blanket to be used directly in a turbine generator. Calculations indicated high temperature superheated steam (811K, 12.5MPa) could be generated within the allowable stresses of presently available piping materials. Based on these turbine inlet conditions, a backpressure of 50 mm HgA, 6-feedwater heaters, 1 reheater and a 6-flow cross compound turbine generator, the overall cycle efficiency is estimated to be 40.5%.