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UTSG-2—A Theoretical Model Describing the Transient Behavior of a Pressurized Water Reactor Natural-Circulation U-Tube Steam Generator

Alois Höld

Nuclear Technology / Volume 90 / Number 1 / April 1990 / Pages 98-118

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34389

An advanced nonlinear transient model for calculating steady-state and dynamic behaviors of characteristic parameters of a Kraftwerk Union-type vertical natural-circulation U-tube steam generator and its main steam system is presented. This model has been expanded due to the increasing need for safety-related accident research studies. It now takes into consideration the possibilities of dryout and superheating along the secondary side of the steam generator. The resulting theoretical model is the basis of the digital code UTSG-2, which can be used both by itself and in combination with other pressurized water reactor transient codes, such as ALMOD-3.4, ALMOD-4, and ATHLET.