Ignitor neutronics and activation

P. Batistoni, P. Corsaro, S. Rollet, M. Zucchetti

Research output: Contribution to journalArticle

6 Citations (Scopus)


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.
Original languageEnglish
Pages (from-to)53 - 68
Number of pages16
JournalFusion Engineering and Design
Issue number1
Publication statusPublished - 1996
Externally publishedYes


All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Materials Science(all)
  • Nuclear Energy and Engineering
  • Mechanical Engineering

Cite this

Batistoni, P., Corsaro, P., Rollet, S., & Zucchetti, M. (1996). Ignitor neutronics and activation. Fusion Engineering and Design, 31(1), 53 - 68. https://doi.org/10.1016/0920-3796(95)00421-1