Luigi Petrizzi

Articles in Scholarly Journals [Incomplete List]

  1. Neutronics design and supporting experimental activities in the EU
    Fusion Engineering and Design, vol. 81, no. 8-14, pp. 1169–1181, 2006
  2. Neutronics experiment for the validation of activation properties of DEMO materials using real DT neutron spectrum at JET
    Fusion Engineering and Design, vol. 81, no. 8-14, pp. 1485–1490, 2006
  3. Benchmarking of Monte Carlo based shutdown dose rate calculations applied in fusion technology: From the past experience a future proposal for JET 2005 operation
    Fusion Engineering and Design, vol. 81, no. 8-14, pp. 1417–1423, 2006
  4. Nuclear analyses of some key aspects of the ITER design with Monte Carlo codes
    Fusion Engineering and Design, vol. 74, no. 1-4, pp. 133–139, 2005
  5. Benchmarking of Monte Carlo based shutdown dose rate calculations for applications to JET
    Radiation Protection Dosimetry, vol. 115, no. 1-4, pp. 80–85, 2005
  6. Neutronics benchmark experiment on tungsten
    Journal of Nuclear Materials, vol. 329-333, pp. 683–686, 2004
  7. Sensitivity and uncertainty analyses of 14 MeV neutron benchmark experiment on silicon carbide
    Fusion Engineering and Design, vol. 69, no. 1-4, pp. 437–442, 2003
  8. Comprehensive activation calculations of reference materials for long term reactor concepts
    Fusion Engineering and Design, vol. 69, no. 1-4, pp. 593–599, 2003
  9. Analysis of dose rate experiment: comparison between FENDL, EFF/EAF and JENDL nuclear data libraries
    Fusion Engineering and Design, vol. 69, no. 1-4, pp. 649–654, 2003
  10. A breeding blanket in ITER-FEAT
    Fusion Engineering and Design, vol. 69, no. 1-4, pp. 315–319, 2003
  11. Benchmark analysis of neutronics performances of a SiC block irradiated with 14 MeV neutrons
    Fusion Engineering and Design, vol. 63-64, pp. 475–479, 2002
  12. Design of plasma facing components for the ITER feat divertor
    Fusion Engineering and Design, vol. 61-62, pp. 153–163, 2002
  13. European achievements for ITER high heat flux components
    Fusion Engineering and Design, vol. 56-57, pp. 173–178, 2001
  14. Design of a welded box divertor cassette for ITER FEAT
    Fusion Engineering and Design, vol. 56-57, pp. 239–242, 2001
  15. Experimental validation of shut down dose rates calculations inside ITER cryostat
    Fusion Engineering and Design, vol. 58-59, pp. 613–616, 2001
  16. Neutron streaming experiment at FNG: results and analysis
    Fusion Engineering and Design, vol. 51-52, no. 1-4, pp. 653–661, 2000
  17. Sensitivity and uncertainty analysis performed on a 14-MeV neutron streaming experiment
    Fusion Engineering and Design, vol. 51-52, no. 1-4, pp. 843–848, 2000
  18. Results from the CDE phase activity on neutron dosimetry for the international fusion materials irradiation facility test cell
    Fusion Engineering and Design, vol. 51-52, no. 1-4, pp. 331–338, 2000
  19. ITER reference breeding blanket design
    Fusion Engineering and Design, vol. 46, no. 2-4, pp. 177–183, 1999
  20. Neutronics experiment on a mock-up of the ITER shielding blanket at the Frascati Neutron Generator
    Fusion Engineering and Design, vol. 47, no. 1, pp. 25–60, 1999
  21. Neutronics experiment on a mock-up of the ITER shielding system at the Frascati neutron generator (FNG)
    Fusion Engineering and Design, vol. 42, no. 1-4, pp. 255–260, 1998
  22. Analysis of integral experiments on stainless steel shields for the validation of the FENDL library
    Fusion Engineering and Design, vol. 37, no. 1, pp. 39–48, 1997
  23. International benchmark tests of the FENDL—1 nuclear data library
    Fusion Engineering and Design, vol. 37, no. 1, pp. 9–21, 1997
  24. Convertible liquid metal blankets for ITER with Pb-17Li as breeding material
    Fusion Engineering and Design, vol. 27, no. 1-2, pp. 353–362, 1995
  25. Activation of TZM and stainless steel divertor materials in the NET fusion machine
    Journal of Nuclear Materials, vol. 212-215, pp. 644–648, 1994
  26. The stainless steel bulk shielding benchmark experiment at the Frascati Neutron Generator (FNG)
    Journal of Nuclear Materials, vol. 212-215, pp. 1724–1728, 1994