An existing geometric and fluid-fluid scaled facility is applied to investi
gate the transport of berated safety injection (SI) fluid in the Westinghou
se AP600 reactor vessel during a main steam-line rupture (MSLR) event. The
AP600 reactor has coaxial injection into the vessel downcomer rather than t
he cold-leg cross-flow injection typical of operating power reactors. This
gas-flow test facility has unique derail in the representation of the SI no
zzle-to-core inlet path most important to SI transport. Analysis of the tra
nsport phenomena expected in the reactor and the scaled facility, given MSL
R conditions, indicates that both buoyancy and turbulent diffusion can have
comparable influences on SI transport. It is shown that different reactor-
to-experiment velocity ratios are required to scale each phenomenon. Tests
are performed to evaluate transient SI fluid concentration at the core inle
t using the appropriate velocity ratios to scale buoyancy and diffusion. Tw
o asymmetric loop-flow boundary conditions representative of the MSLR event
as well as a symmetric flow condition are applied While no one test result
is fully similar to the expected reactor transport, this ensemble of rests
provides data that are valuable for AP600 numerical model benchmarking.