Research Article
Antineutrino Flux from the Laguna Verde Nuclear Power Plant
Table 3
Parameters of the BWR core used in the simulation with DRAGON code [
20].
| Thermal power (of each reactor) | 2027 MWth |
| Specific power (of each reactor) | 20.43 MW/ton |
| Moderator | Demineralized water | Temperature | 600 K | Density | 0.720 g/cm3 |
| Coolant | Demineralized water | Temperature | 400 K | Density | 0.720 g/cm3 |
| Fuel assemblies | 444 | Red assemblies | 68 | Blue assemblies | 96 | Yellow assemblies | 280 |
| Single unit cell () | 1.295 cm × 1.295 cm |
| Fuel bars per assembly | 92 | Composition | UO2/UO2-Gd2O3 | Cladding | Zircaloy 2 | Zircaloy density | 5.821 g/cm3 | Zircaloy temperature | 600 K | Fuel temperature | 900 K | Fuel density | 10.079 g/cm3 | Fuel bar radius () | 0.438 cm | Zircaloy cladding radius () | 0.513 cm | Fuel bar height | 400 cm |
| Coolant pipes per assembly | 2 | Composition | Zircaloy 2 | Pipe radius (occupied by water) | 1.0 cm | Pipe radius (occupied by Zircaloy) | 1.2 cm |
|
|