This paper reports on the design, modelling and development of a compu
ter code for a blanket and its thermal-hydraulic and tritium mass tran
sport capability and performance. The model includes all the heat and
mass transfer processes that occur in the blanket and allows examinati
on of the thermal behaviour with time and under varying thermal load,
including the prediction of tritium mass transfer, release, diffusion
and recovery behaviour, and corresponding rates in the blanket. The mo
del is used to perform scoping and technology assessment studies for p
ower plant relevant parameters. The model and code also have the capab
ility of analysis of accident scenarios of candidate blanket concepts
and testing of the neutronic performance of various material configura
tions.