Neutronics analysis of the ITER-CXRS-port plug

A sophisticated simulation method was developed and successfully applied in order study the impact of the radiation and the neutron field on the port plug structures and components of ITER encompassing the CXRS diagnostic system. The method allows the determination of neutron fluxes, heating rates, radiation damages (dpa, helium production) as well as in combination with the activation code FISPACT the activation and dose rate of the individual inserts in a high level of resolution. The distributions of neutron fluxes, direct neutron and gamma heating, material damage (dpa) and helium production within different components of the CXRS are presented at the annual meeting on nuclear technology 2013. (orig.)