Main core design libraries developed at CEA.
|Fuel/Reactor||Initial U-235 or Pu enrichment Maximum burnup||Note|
|PWR UOX (fuel)||Up to 5%
Up to 100 GWd/t
|17 × 17 but also 14 × 14, 15 × 15, 16 × 16, 18 × 18, and Reprocessing uranium based fuel, etc, …|
|Subassembly structures||Up to 5% (UOX PWR) and 12% (MOX, FBR) Up to 100 GWd/t||Libraries divided into different parts: Top nozzle, spring plug, plenum, clads and grids, bottom end plug, bottom nozzle|
|BWR UOX||Up to 4.5 % Up to 72 GWd/t||9 × 9, 8 × 8. Libraries divided into different parts to account for axial heterogeneity (void fraction or initial composition). Burn-up also has an influence on axial power level.|
|PWR MOX||Up to 12% Up to 100 GWd/t||17 × 17 but also 14 × 14, 15 × 15, 16 × 16 Effects of initial plutonium composition on cross section sets are taken into account.|
|BWR MOX||Up to 6.1 % Up to 50 GWd/t||Libraries divided into different parts to account for axial heterogeneity (void fraction or initial composition).|
|Heavy Water||Up to 94 % Up to 440 GWd/t||French and foreign experimental old reactors|
|Fast Reactor||Up to 25 % Up to 200 GWd/t||Phenix, RAPSODIE, European Fast Reactor|
|Gas Cooled Reactor||Up to 1,7% Up to 11 GWd/t||Metallic fuel, Graphite moderator, Low enrichment uranium|
|MTR||Up to 94 % Up to 1000 GWd/t||Rods, flat or cylindrical plates experimental facilities|
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