[en] Steady state critical heat flux (CHF) tests have been performed on electrically heated rod bundles simulating the central region of the Loss-of-Fluid Test (LOFT) nuclear reactor core. Previously reported steady state CHF tests have shown that cladding surface thermocouples on LOFT fuel rods reduce the critical heat flux over the pressure range of 13.8 to 16.5 MPa. Reported are additional steady state CHF tests which have been performed to determine the effects of rod external thermocouples on CHF over the ranges of pressure (about 11 MPa) and quality (30 to 40 percent) where CHF is predicted to occur in LOFT during blowdown operation and to determine if sufficient data could be obtained to develop a CHF correlation to predict critical heat fluxes in the LOFT core for blowdown operation