Neutronics analysis and nuclear heating measurement up to the TFC in a mock-up of the ITER inboard shield

M. Angelone, P. Batistoni, F. Moro, M. Pillon, R. Villari, M. Laubenstein, M. Loughlin

Research output: Contribution to journalArticle

7 Citations (Scopus)


A mock-up of ITER including the inboard shield, the vacuum vessel and the coil region, was set up at ENEA Frascati and irradiated with 14 MeV neutrons produced by the Frascati Neutron Generator (FNG). The mock-up dimensions and materials composition are consistent with the current ITER design. The primary objective of the experiment was to validate the MCNP calculations (C) of nuclear heating measured (E) in the region corresponding to the ITER Toroidal Field (TF) coil. An accuracy on C/E ratio ≤±10% was required. The neutronics and shielding properties of the mock-up were also studied throughout the measurement of selected activation reaction rates up to about 1 m depth. Due to the very low activity induced in the foils, the measurements in the deepest experimental positions were performed at the underground low background facility of the Laboratori Nazionali del Gran Sasso, using ultra-low background high purity germanium (HPGe) detectors. The measured reaction rates and nuclear heating were thus compared with the results of the Monte Carlo code MCNP5 coupled with the FENDL-2.1 library. © 2012 EURATOM ENEA Association.
Original languageEnglish
Pages (from-to)910 - 915
Number of pages6
JournalFusion Engineering and Design
Issue number5-6
Publication statusPublished - Aug 2012
Externally publishedYes


All Science Journal Classification (ASJC) codes

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

Cite this

Angelone, M., Batistoni, P., Moro, F., Pillon, M., Villari, R., Laubenstein, M., & Loughlin, M. (2012). Neutronics analysis and nuclear heating measurement up to the TFC in a mock-up of the ITER inboard shield. Fusion Engineering and Design, 87(5-6), 910 - 915.