Analysis of reactivity induced accidents at Pakistan Research Reactor-1

Conversion of Molybdenum-99 production process to low enriched uranium: Neutronic and thermal hydraulic analyses of HEU and LEU target plates for irradiation in Pakistan Research Reactor-1

“…Calculation of pressure drops (entrance, frictional, sudden contraction, sudden expansion, etc.) along the holder in water box showed that for example that a hole of 5 cm diameter size would allow coolant flow rate of 16.3 m 3 /h that would be about 1.7% of total core flow rate [18][19][20] through the core. Coolant velocity in the target fuel channel was calculated to be 4.08 m/s with this hole size (5 cm diameter) and was adopted for the thermal calculations.…”

Dose rate reduction in the Pakistan Research Reactor-1 by the utilization of high-density low enriched uranium fuel

“…axial power profile of the core was multiplied by the radial power peaking factor and the engineering hot channel factor 1.584 to account for the various uncertainties (Bokhari et al, 2002). All the calculations were performed with a water inlet temperature of 38 C and inlet pressure of 1.712 bars.…”

“…The effective coolant flow rate reported for the existing PARR-1 core is 950 m 3 /h, i.e. 95% of the full flow rate (Bokhari et al, 2002). Therefore, to calculate the maximum coolant velocity, we recalculated the coolant velocity in the coolant channels on 950 m 3 /h effective flow rate.…”