- F.Alicino, G.B.Bozzo, C.Dini - "Sistema di chiusura a tenuta per un canale di potenza di un reattore nucleare ad acqua pesante" - VI conferenza nazionale AIMETA, Genova, 7-9 ottobre 1982. Read paper
- F.Alicino, G.Zampini - "Progressive plastic deformation in metallic liner of concrete structures” - 7th International Conference on SMIRT, Chicago (USA), August 22-26, 1983. Read paper
- F.Alicino, G.Zampini - "Integrity assessment for a zircaloy-2 pressure tube with fretting corrosion defects" - 5th International Conference on Pressure Vessel Technology (ASME), San Francisco (USA), September 9-14, 1984. Read paper
- F.Alicino, S.Chiocchio - "A methodology to analyze the structural behaviour at high temperature of heavy water moderated reactor pressure tubes" - 2nd International Seminar on Standards and Structural Analysis in Elevated Temperature Applications for reactor Technology, Venice, October 15-17, 1986. Read paper
- F.Alicino, G.Zampini, M.Morysse - "An original leak test for the Cirene nuclear plant" - 9thInternational Conference on SMIRT, Lausanne, August 17-21, 1987 and on SMIRT special issue of RES MECHANICA. Read paper
- F.Alicino, E.Capurro, A.Corvi, G.Majorana, S.Reale - "Valutazione con la meccanica della frattura dell’accettabilità di difetti secondo i controlli non distruttivi"- IV convegno nazionale Gruppo Italiano Frattura (IGF), Milano, 26-27 maggio 1988. Read paper
- F.Alicino, E.Capurro, A.Corvi, G.Majorana, S.Reale - "The Use of Fracture Mechanics for the Evaluation of NDE Flaw Acceptance Standards"- CSNI workshop on complementary roles of fracture mechanics and NDE in safety assessment of components, Wuerenlingen (Switzerland), October 3-5, 1988. Read paper
- F.Alicino, S.Chiocchio, F.Fardi, G.Zampini - "Once-through straight tube steam generators subject to severe thermal transients compensation systems optimization" - 10thInternational Conference on SMIRT, Los Angeles (USA), August 14-18, 1989. Read paper
- F.Alicino, S.Chiocchio - "Fracture Mechanics evaluation of credible breaks in Heavy Water Reactor liquid and steam feeder primary lines" - 10thInternational Conference on SMIRT, Los Angeles (USA), August 14-18, 1989. Read paper
- F.Alicino, S.Cardini - "Fast Breeder Reactors secondary piping potential sodium leakage rate assessment" - 10thInternational conference on SMIRT, Los Angeles (USA), August 14-18, 1989. Read paper
- F.Alicino, E.Capurro, A.Corvi, S.Reale - "An overview of the PSI flaw acceptance standards based on the R6 assessment" - European Symposium on Elastic-Plastic Fracture Mechanics: elements of defect assessment, Freiburg, Federal Republic of Germany, October 9-12, 1989.
- F.Alicino, R.Antoni - "Individuazione delle modalità di ispezione in servizio per apparecchi di sollevamento con i metodi della meccanica della frattura" - IGF6, VI Convegno Nazionale Gruppo Italiano Frattura, Ancona, 7-8 giugno 1990. Read paper
- F.Alicino, E.Capurro, A.Corvi, S.Reale - "An overview of the NDE flaw acceptance standards based on the R6 assessment" - ECF8, Eighth European Conference on Fracture, Torino, October 1-5, 1990.
- F.Alicino, L.Cornaggia - "Il criterio leak before break nell'impiantistica nucleare" - Atti del VII Convegno Nazionale del Gruppo Italiano Frattura, Firenze, 13-14 Giugno 1991. Read paper
Exitus Acta Probat