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University of Nebraska–Lincoln: Home of ANS’s newest student section
Following official confirmation in June at the American Nuclear Society’s 2025 Annual Conference, the University of Nebraska–Lincoln has kicked off its first year as the newest ANS student section.
Joseph M. Kelly, Charles W. Stewart, Judith M. Cuta
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 246-259
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34746
Articles are hosted by Taylor and Francis Online.
The VIPRE-02 code is a thermal-hydraulic analysis code designed to model steady-state conditions and operational transients in light water reactor cores and vessels. It uses a two-fluid representation of two-phase flow that solves conservation equations for mass, momentum, and energy for each phase. The code uses a subchannel formulation of the conservation equations but also contains an optional three-dimensional (r-θ coordinates) representation of the lower plenum for vessel modeling. The six-equation formulation is solved implicitly, by a modified Gauss-Seidel iteration procedure, and has no time step size limitation for stability. Models for phase interaction based on flow regime mapping are provided that use empirical models and correlations for heat and mass transfer at the interface and vapor generation. In addition, the code contains as an option a dynamic flow regime model, which uses an interfacial area transport equation to determine the phase interaction terms.