The neutron and gamma fluxes in all the main components of the projected Ignitor tokamak are calculated and discussed. The results are obtained using the 3-D Monte Carlo code MCNP with a detailed description of the device geometry and an accurate representation of the neutron source. The neutron-induced radioactivity, contact dose rates, and radiation damage of the relevant parts of the device are then derived. The consequences on the life and maintenance of device components, the exposure of personnel working in tokamak environments, and the disposal of components after shutdown are described.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Materials Science(all)
- Nuclear Energy and Engineering
- Mechanical Engineering