SNF Spent Nuclear Fuel
Studsvik Scandpower's integrated supplement for back-end fuel cycle analysis with applications to:
Calculation of radiation source terms in connection with short term storage, transportation/intermediate storage and final storage (repository) of fuel assemblies.
Calculation of decay heat during shutdown or of assemblies in the fuel pool
Calculation of isotopic inventories in spent fuel (safeguards, etc.)
The calculations are performed with pin by pin tracking via CASMO-4 and SIMULATE-3 calcualtions, thus reflecting the actual oeprating history of the pins (rather than estimated history).
The result vs. conventional alternative synthesis methods:
Reduced cooling time implies cost saving potential
Earlier cask loadings improves pool capacity and shortens the plant operation after final plant shutdown
Extensively benchmarked against CLAB measurements from Scandinavia (16 BWR and 33 PWR assemblies)