3-D neutronics and shielding analyses have been performed for the dive
rtor region of the ITER interim design. The peak neutron wall loading
in the divertor region is 0.6 MW/m(2) at the divertor cassette dome. T
he total nuclear heating in the 60 divertor cassettes is 102.4 MW. The
peak helium production in the VV behind the pumping ducts is 0.5 He a
ppm/FPY implying that rewelding might be feasible. The total nuclear h
eating in the parts of the TF coils in the divertor region is only 2.1
kW.