1. Structural analysis for the determination of design variables of spent nuclear fuel disposal canister
2. (4) Anttila, M., Criticality Safety Calculations for the Nuclear Waste Disposal Canisters, Report POSIVA-96-11, Posiva Oy, Helsinki, Finland, (1996).
3. (5) Anttila, M., Criticality Safety Calculations of the Nuclear Waste Disposal Canisters for Twelve Spent Fuel Assemblies, Working Report 99-03, Posiva Oy, Helsinki, Finland, (1999), p.20.