Abstract
The power excursion characteristics of the Nigeria Research Reactor-1 (NIRR-1) under different reactivity insertion transients have been calculated using PARET/ANL 7.3 code. Experimental data of dynamic experiments performed in NIRR-1 facility during initial startup were used to benchmark the calculated data. For ramp insertion of total cold core excess reactivity of 3.77 mK, the reactor quickly reaches a maximum power of 82.3 kW in 390 s and decreases gradually due to the inherent safety features. The calculated maximum power for this insertion is in good agreement with a measured value of 79.4 kW recorded during the commissioning of NIRR-1. Similarly, moderator temperature for the hottest channel with respect to this transient was calculated to be 63.7 °C which is comparable to a measured value of 63.9 °C. Furthermore, step reactivity insertions of 2.23 mK and an approximately 0.32 mK, a regular criticality experimental check carried out at MNSR facilities by Safeguards Inspectors were accurately simulated.
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