[en] The reservations of international community on utilization of high enriched uranium (HEU) fuel in civil nuclear reactors, it has been planned to design and irradiate low enriched uranium (LEU) fuel plates for Molybdenum-99 production at Pakistan Research Reactor-1 (PARR-1). Safety analysis for the proposed LEU target fuel plate, its irradiation in the core and transportation to the processing plant was performed. Neutronic analyses of the target holder bearing three fuel plates at equal distance from each other, was performed. The activity of the target plates was calculated. Effect of irradiation was studied by placing this holder at different axial positions. It was concluded that the criteria of avoiding Onset of Nucleate Boiling (ONB) is fulfilled for irradiation of the target plates at any vertical position in the water box positioned at C-4. With such arrangement, the results showed that target holder irradiation had safe Departure from Nucleate Boiling Ratio (DNBR) which was greater than 2. The maximum temperature achieved was 104.7 deg. C, which is about 21 deg. C below the clad surface temperature that can initiate nucleate boiling shows the maximum activities of waste and /sup 99/Mo after irradiation. (orig./A.B.)