Research Article
Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl
Table 1
Model specification.
| Property | Unit | Value | Reference |
| Assembly fuel height | cm | 365.76 | [4] | Cladding composition | wt% | Zr-4: Fe/Cr/Zr/Sn = 0.15/0.1/98.26/1.49 | FeCrAl: Fe/Cr/Al = 75/20/5 | Fuel pellet radius | mm | 4.09575 | Gap thickness | μm | 82.55 | Cladding inner radius | mm | 4.1783 | Cladding thickness | μm | 571.5 | Cladding outer radius | mm | 4.7498 | Fuel enrichment | % | 4.9 | P/D | | 1.326 | Cladding IR of guide tube | mm | 5.624 | Cladding OR of guide tube | mm | 6.032 | Number of guide tubes | | 25 | Fuel density | g/cm3 | U3Si2: 11.57 (94.7% theoretical density) | [16] | UO2: 10.47 (95.5% theoretical density) | [4] | Specific power density for reference UO2-Zr | MW/MtU | 38.33 | Coolant density | g/cm3 | 0.7119 | Helium density | g/L | 1.625 (2.0 MPa) | [24] | Cladding density | g/cm3 | Zircaloy-4 cladding: 6.56 | [4] | FeCrAl cladding: 7.10 | Coolant temperature | K | 580 | Fuel temperature | K | 900 | Cladding and gap temperature | K | 600 | Simulation time | EFPD | 1500 | Boron concentration | ppm | 630 | Boundary conditions | | Reflective | Assembly design | | Westinghouse 17 × 17 PWR fuel rod |
|
|
Values only for the reference case.
|