A neutronics mock-up of the ITER inboard shielding system including fi
rst wall, shield-blanket, vacuum vessel and magnetic field coils, was
investigated in order to validate calculational tools used for the ITE
R design and to verify the nuclear performance of the shield by measur
ing neutron and photon flux spectra at two positions inside the bulk a
ssembly. The measured spectra are compared with results from calculati
ons using the Monte Carlo code MCNP-4A and the data library FENDL-1. I
ntegral values such as neutron-induced reaction rates and gamma-heatin
g are calculated on the basis of the experimentally obtained flux spec
tra, and are compared with independent measurements of these data. Hel
ium and hydrogen production rates, as well as the radiation damage rat
e, are determined again by using the measured flux spectra. (C) 1998 E
lsevier Science S.A. All rights reserved.