Overcoming the distortion appears in the production of fuel plate in Material Testing Reactor type (MTR) type fuel is considered an important challenge in safeguard measurements. A methodology is presented using a mathematical model and MCNP code to minimize defects that result from the chemical mixing in U 3 O 8-Al Compact. The mathematical model relates between distance (sampledetector) and the count rate of 185.7 keV gamma energy line that characterize U-235 isotope. The tested samples are compact of uranium oxide and aluminum alloy. The mixing ratio is 48 volume % of U 3 O 8 , and 52 volume % of Al-metal powder. The sample volume is 35.48 cm 3 and its density is 4.8 g/cm 3. The manufacturer data concerning U-235 mass is 0.7785 and 21.3 g. The compact has a parallelpiped shape that has dimensions of 69, 8.5 and 60.5 mm. The used instrument is a High-Purity Germanium detector (HPGe) and the distances between the detector-sample are in the range from 9.5 to 11 cm. Results coming from the model and MCNP-5 complement each other and validated by comparing with declared values. The method could play an important role in safeguards and processes of Quality Control (QC) in the Fuel Manufacturing Pilot Plant (FMPP).