Research Article
Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies
Table 4
Thermodynamic quality and pressure drop in the hot fuel assembly from the CARR reactor.
| Control volume | Core height (mm) | Thermodynamic quality | Pressure (kPa) |
| 1 | 50 | -1.14E-03 | 628.255 | 2 | 100 | -1.13E-03 | 636.55 | 3 | 150 | -1.10E-03 | 644.89 | 4 | 200 | -1.06E-03 | 653.282 | 5 | 250 | -9.90E-04 | 661.732 | 6 | 300 | -9.01E-04 | 670.245 | 7 | 350 | -7.94E-04 | 678.823 | 8 | 400 | -6.78E-04 | 687.463 | 9 | 450 | -5.63E-04 | 696.161 | 10 | 500 | -4.60E-04 | 704.908 | 11 | 550 | -3.70E-04 | 713.696 | 12 | 600 | -2.86E-04 | 722.521 | 13 | 650 | -2.13E-04 | 731.378 | 14 | 700 | -1.54E-04 | 740.261 | 15 | 750 | -1.04E-04 | 749.165 | 16 | 800 | -5.86E-05 | 758.088 | 17 | 850 | -1.86E-05 | 767.029 |
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