A complete neutronic analysis has been performed for the design of the in-vessel coil systems using the MCNP5 Monte Carlo Code in a full 3-D geometry. A detailed geometry of ELM and VS coils based on the latest design specifications has been integrated into the latest version of 40° sector of ITER MCNP model. Nuclear heating and helium production in the coils, absorbed dose in the insulator, dpa and transmutation of copper-alloy and neutron fluxes have been calculated. Neutron spectra have been used as input for an activation analysis performed with FISPACT inventory code for safety analysis and waste classification. The impact of the gaps between blanket modules and of the manifolds on the nuclear parameters has been evaluated as well as the effect on vacuum vessel reweldability. Different options for the conductor and the insulator have been examined. © 2011 EURATOM. Published by Elsevier B.V. All rights reserved.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
Villari, R., Petrizzi, L., Brolatti, G., Daly, E., Loughlin, M., Martin, A., ... Polunovskiy, E. (2011). Three-dimensional neutronic analysis of the ITER in-vessel coils. Fusion Engineering and Design, 86(6-8), 584 - 587. https://doi.org/10.1016/j.fusengdes.2010.12.004