Abstract
Calculations of neutron and gamma transport were carried out with the MCNP-4A code for some optical diagnostic systems located in the upper and equatorial ports of the reactor ITER. The main emphasis was placed on gamma-neutron fluxes and energy deposition in mirrors, quartz windows and optical fibres. Neutron and gamma spectra at primary vacuum windows were calculated for the purpose of determining accurately their possible transparency degradation in ITER on the basis of irradiation test data. The effectiveness of neutron shielding was considered from a viewpoint of radiation safety. A similar analysis was done for the CXRS diagnostic system: the nuclear energy deposition in mirrors and the dose rate responses at toroidal field coils were calculated.
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