Modelling effects on axial neutron flux in a Tokamak device

Using Monte Carlo N-Particle (MCNP5), three different Tokamak models using different geometries were simulated, maintaining some basic parameters from the ITER design. The neutron flux and the reaction rates were obtained over different volumes: FW, divertor and along the different device walls. The three geometries were compared under the same conditions. The results showed the behaviour of the neutron flux spectra along the different walls, as well as, the most suitable model taking in consideration the different analyses and the final purpose of adding a transmutation layer. Finally, the chosen geometry will be used to analyse the burnup, buildup, decay, and processing of material under irradiation. •Three different Tokamak models using different geometries were simulated.•The neutron flux and the reaction rates were obtained over different volumes.•The flux energy maps of the inboard and outboard first wall were analysed.•A possible transmutation blanket position was obtained.