Home / Publications / Journals / Nuclear Technology / Volume 54 / Number 3
Nuclear Technology / Volume 54 / Number 3 / September 1981 / Pages 358-363
First International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32780
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The RETRAN system analysis code has been used to simulate a Three Mile Island Unit 2 overfeeding transient that occurred during a plant startup. Excessive feedwater was fed into the steam generators and resulted in a sudden depressurization of the reactor coolant system (RCS). The reactor tripped on low RCS pressure and safety injection was initiated. The RETRAN simulation of this event shows the same trends and predicts the same sequence of events as the plant data and thus develops a reliable understanding of the relationship between the primary RCS and the secondary feed and steam systems. The model developed is useful in studying the margin to protective system limits during disturbances at low power.