Research Article
Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code
Table 4
Transient core averaged results for Cases A, B, and D.
| Parameters | Results | Reference | NODAL3 | AM | IQM |
| Case A | Fission power relative to nominal (), % | C1 | 35.56 | 35.39 (0.48%) | 35.42 (0.39%) | Time of maximum fission power, s | 82.14 | 83.24 (1.34%) | 83.32 (1.44%) | Average coolant outlet temperature (), °C | C3 | 295.3 | 294.8 (0.17%) | 294.8 (0.17%) | Average core Doppler temperature (), °C | C4 | 358.7 | 359.5 (0.22%) | 359.8 (0.31%) |
| Case B | Fission power relative to nominal (), % | C1 | 134.80 | 110.67 (17.90%) | 112.16 (16.80%) | Time of maximum fission power, s | 34.30 | 34.71 (1.20%) | 34.74 (1.28%) | Average coolant outlet temperature (), °C | C3 | 290.5 | 290.3 (0.07%) | 290.3 (0.07%) | Average core Doppler temperature (), °C | C4 | 315.2 | 313.6 (0.51 %) | 313.8 (0.44%) |
| Case D | Fission power relative to nominal (), % | C1 | 96.85 | 109.23 (12.78%) | 110.60 (14.20%) | Time of maximum fission power, s | 39.40 | 39.91 (1.29%) | 39.93 (1.35%) | Average coolant outlet temperature (), °C | C3 | 290.0 | 290.3 (0.10%) | 290.3 (0.10%) | Average core Doppler temperature (), °C | C4 | 312.6 | 313.7 (0.35%) | 314.0 (0.45%) |
|
|
Note. Number in parentheses are the absolute value of relative deviation of NODAL3 with the reference.
|