Thermal-hydraulic analysis techniques for axisymmetric pebble bed reactor cores |
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| Authors: | K.R. Stroh R.J. Jiacoletti H.G. Olson |
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| Affiliation: | 1. Reactor and Advanced Heat Transfer Technology Group, Energy Division, Los Alamos Scientific Laboratory, Los Alamos, NM 87545, USA;2. Design Engineering Division, Los Alamos Scientific Laboratory, Los Alamos, NM 87545, USA;3. Mechanical Engineering Department, Colorado State University, Fort Collins, CO 80523, USA |
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| Abstract: | A mathematical model for the analysis of coupled thermal-hydraulic problemsin steady-state pebble bed nuclear reactor cores is presented. The bed has been treated macroscopically as a generating, conducting porous medium. The model uses a nonlinear Forchheimer-type relation between the coolant pressure gradient and mass flux, and new coefficients of the viscous and inertial loss terms are presented. The remaining equations in the model make use of continuity and thermal energy balances on the solid and fluid phases. None of the usual simplifying assumptions such as constant properties, constant velocity flow or negligible conduction and/or radiation are used. A computer program based on this model has been constructed; it has been validated by comparing predictions with measured values of previous experiments. Validation of the nonlinear fluid flow model is reported in a companion paper. |
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