Open Access
Table 2
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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