Development of Modeling Capabilities for the Analysis of Supercritical Water-Cooled Reactor Thermal-Hydraulics and Dynamics Page: 4 of 13
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models have been converted into a non-dimensional form based on the ratios of actual-to-
critical pressure and actual-to-critical temperature (using the absolute temperature scale).
Furthermore, similar models have also been developed for supercritical carbon dioxide
(CO2).
For computational purposes, all major thermo-fluid properties of both CO2 and water at
supercritical pressures have been converted into analytical expressions based on a spline-type
formulation given by
P(T, p) = a 1 (P) + bQ (P)T + c 1 (P)T2 +d , (P)T3 for T T <1, (i = 1,2,...N)
where ' represents one of the following properties: density, p, specific heat, cp, dynamic
viscosity, p, thermal conductivity, k, and Prandtl Number, Pr, and N is the total intervals
needed to sufficiently resolve the property dependence on temperature.
The new models were first validated for fixed pressures; then the effect of pressure has been
be accounted for as an independent variable in a manner similar to that used for temperature
variations. Typical results showing a comparison between the new models and experimental
data are shown in Figure 3.
800 80
25 MPa
700 -NIST 70
600 ---Model 60 -
M 500 50
400 40
a 300 30
200 20
100 10
0 0
370 375 380 385 390 395 400
T [0C1
Figure 3. Temperature-dependent density and specific heat of water at a supercritical pressure
of 25 MPa; a comparison between the current model and the official NIST data.
(3) Improvements in the NPHASE-CMFD Computational Solver
As a result of the present work, several contributions have been made to upgrade some of the
existing models in the NPHASE-CMFD code, and to develop and implement new models
pertinent to the objectives of the current project.
The new models include:
- Thermodynamic property routines for water and carbon dioxide at supercritical pressures;
see Item (2) above.4
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Podowski, Michael Z. Development of Modeling Capabilities for the Analysis of Supercritical Water-Cooled Reactor Thermal-Hydraulics and Dynamics, report, April 16, 2009; United States. (https://digital.library.unt.edu/ark:/67531/metadc929425/m1/4/: accessed May 8, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.