1. Neutron fluxes computed by Ansaldo have been provided by ENEA in the frame of the ENEA-Politecnico contract “Studi inerenti la valutazione di impatto ambientale ed il rapporto di sicurezza di Ignitor”, 2006.
2. ENDF/B-VII.0 data processed with NJOY-99.259 for radiation damage calculations, NEA/OECD Data Bank, http://www.nea.fr/dbdata/process/, July 2008.
3. J. Sanz, O. Cabellos, N. García-Herranz, Inventory Code for Nuclear Applications: User's Manual V. 2008, December 2008 (NEA-1839 ACAB-2008).
4. Effect of activation cross-section uncertainties in the assessment of primary damage for MFE/IFE structural materials;Cabellos,2007
5. See web site: http://www.frascati.enea.it/ifmif/.