[en] A linear elastic analysis of the LOFT reactor internals was conducted to demonstrate the structural integrity of the reactor system during two Loss-of-Coolant Accidents (LOCA). Time dependent pressure transients were used to predict the behavior of the internals for the following LOCA's: 14'' 15 msec reactor vessel nozzle hot leg break; and 14'' 15 msec reactor vessel nozzle cold leg break. For the most severe design LOCA (Cold Leg LOCA), the LOFT reactor internals can safely withstand stresses due to a combination of pressure transient loading and seismic loading