[en] Best-estimate predictions of LOFT fuel rod behavior during the first LOFT nuclear test series have been made with both RELAP/FLOOD4/FRAP-T and RELAP/SCORE/MOXY computer code combinations. The purpose of the predictions are to test the best-estimate code accuracy by comparison of predictions to subsequent test data and to develop plans for post-test fuel replacements and examinations. The FRAP-T3 computer code was utilized which couples the thermal, mechanical, internal gas, and material property behavior of a nuclear rod during various postulated accident sequences. The cladding deformation models account for elastic-plastic behavior. FRAP-T3 requires coolant conditions to be specified as input boundary conditions. The coolant conditions for the blowdown and refill phases of a loss-of-coolant experiment (LOCE) were calculated with RELAP4/MOD6 and for the reflood portion with FLOOD4