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Validation of the ATR-SINDA Fuel Plate Model Using Advanced Test Reactor Startup Data

Steven T. Polkinghorne

Nuclear Technology / Volume 108 / Number 3 / December 1994 / Pages 395-412

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35022

The ability of the ATR-SINDA fuel plate model to predict the thermal behavior of Advanced Test Reactor (ATR) fuel plates under steady-state and transient conditions is demonstrated. Computer-generated results from ten steady-state calculations and two transient calculations are compared with experimental data obtained during ATR startup tests. The calculations simulate natural convection, forced convection, flow reversal, and flow instability in specially instrumented fuel elements. Calculated temperatures are generally within 10 K of measured temperatures, confirming that ATR-SINDA is suitable for analyzing plate-type fuel.