Neutronics for ITER diagnostic systems and ports

Three dimensional neutronic analysis was performed to determine effects of radiation streaming through ITER ports with installed shield plugs and different diagnostic equipment. Studied were Neutral Particle Analyser (NPA), Neutron Camera Array and LIDAR plasma diagnostic in upper and midplane ports. The purpose of the analysis was an estimation of nuclear radiation level in the vicinity of ports due to radiation streaming, radiation responses in TF and PF coils, activation and dose rate levels. Some study was performed to estimate radiation level at locations of diagnostic sensors in NPA behind ITER biological shield. All radiation transport calculations were carried out using 3-dimensional code MCNP-4A with pointwise FENDL-1 library. Activation calculations were performed using FISPACT inventory code. The obtained results can be used in designing of the studied diagnostics.