Neutronics analyses for the ITER extended performance ECRH launcher

The neutronics aspects of radiation shielding analyses in support for development of the ITER extended performance (EP) ECRH launcher are addressed in the paper. Correspondence of the launcher design to the ITER nuclear regulations is demonstrated for fulfillment of the nuclear quality assurance (QA) programme. The human safety issues (shutdown dose rates) and nuclear design limits are envisaged in the paper and compared from other author´s results. The radiation transport calculations were performed by the Monte Carlo N-particle code MCNP-5 in 3D models. The models are automatically converted from the dedicated CAD (CATIA) models of the launcher by means of the McCad interface. Size-and-shape effects of the internal shield hole on the nuclear responses in the launcher itself and in the vicinity components (Poloidal Field Coil, Vacuum Vessel, and Toroidal Field Coil) are reported. The paper includes performance assessments of the MCNP-5 parallel computations on the FZK CampusGrid cluster in terms of speed up and efficiency. The recommendations on how to improve the performance of the parallel computations are provided. It is proven that nuclear analyses are necessary to perform at any step of the ECRH launcher design development.