Page 212 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

System thermal hydraulics for liquid metals 183

additional validation models based on an FFTF passive safety demonstration test con-
ducted in 1986.
Unique features include:

l single-pin characteristic channel models for rapid evaluation of transients;
l detailed thermal-hydraulic subchannel models for fuel assemblies;
l support for liquid-metal coolants such as sodium, NaK, lead, and LBE, as well as other
single-phase coolants;
l full-plant coolant system models to simulate passive heat removal and inherent safety;
l oxide and metallic fuel models for fuel melting, in-pin motion, pin failure, and ex-pin fuel
dispersal and freezing;
l additional metallic fuel models for fuel-clad eutectic formation and cladding failure;
l reactor point kinetics with comprehensive treatment of reactivity feedback effects as per
first-order perturbation theory;
l high-fidelity decay heat models;
l built-in support for American Nuclear Society standard decay heat properties;
built-in support for alternative coolants in decay heat removal loops;
l
support for line-based comments in input files;
l
support for coupling to third-party computational fluid dynamics tools (such as STAR-
l
CCM+) for representing thermal stratification in large volumes;
support for coupling to DIF3D-K for reactor spatial kinetics;
l
l detailed reactor and plant control systems.
References

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