The Los Alamos National Laboratory is developing the Transient Reactor Analysis Code (TRAC) to provide advanced best-estimate predictions of postulated accidents in light-water reactors. The TRAC-PF1/MOD1 program provides this capability for pressurized water reactors and for many thermal-hydraulic test facilities. The code features either a one- or a three-dimensional treatment of the pressure vessel and its associated internals, a two-fluid nonequilibrium hydrodynamics model with a noncondensable gas field and solute tracking, flow-regime-dependent constitutive equation treatment, optional reflood tracking capability for bottom-flood and falling-film quench fronts, and consistent treatment of entire accident sequences including the generation of consistent initial conditions. The stability-enhancing two-step (SETS) numerical algorithm is used in the one-dimensional hydrodynamics and permits this portion of the fluid dynamics to violate the material Courant condition. This technique permits large time steps and, hence, reduced running time for slow transients.

/pdf/trac-pf1-mod1-an-advanced-best-estimate-computer-program-for-34rob85tra.pdf

TRAC-PF1/MOD1: an advanced best-estimate computer program for pressurized water reactor thermal-hydraulic analysis

Flow and heat transfer regimes during quenching of hot surfaces

Prediction methods for dispersed flow film boiling

Modeling of reflooding

https://publikationen.bibliothek.kit.edu/270041831/3813628

Development and validation of a transition boiling model for RELAP5/MOD3 reflood simulation

The article is a general description of core behavior during the reflooding phase of the LOCA. A succession of heat-transfer and two-phase flow regimes moves along the rod bundle during reflooding of the core. Parametric ranges and other features of transient reflooding experiments that have been conducted with rod bundles and in simple single-channel geometries are tabulated. Experimental findings and parametric trends are summarized and explained. Core heat-transfer and hydrodynamics analysis methods incorporated in emergency core-cooling system evaluation models used for licensing purposes are reviewed, and the work on more advanced models that attempt to estimate core heat-transfer coefficients on the basis of calculated local flow conditions is noted.

Reflooding phase of the LOCA in PWRs. Part I: core heat transfer and fluid flow

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Reflooding phase of the LOCA in PWRs. Part I: core heat transfer and fluid flow