Home / Publications / Journals / Nuclear Technology / Volume 61 / Number 2
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 181-192
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33189
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In contrast to large break, loss-of-coolant accident analysis, analysis of plant operational transients requires an accurate steady-state initialization and proper modeling of the actions of plant control systems during the transient. To assess the basic capability of the RETRAN-02 computer code to calculate operational transient phenomena, posttest analyses of the loss-of-fluid test anticipated transient tests L6-1, L6-2, L6-3, L6-5, and L9-1 were performed. The comparisons of the RETRAN-02 calculations with the experimental data show the importance of matching both the initial conditions and the boundary conditions. The results indicate that RETRAN-02 is capable of calculating operational transient phenomena with reasonable accuracy.