Critical and Power Experiments on the Low-Enriched Uranium Core of the Upgraded Pakistan Research Reactor-1
Saleem A. Ansari, Masood Iqbal, Liaqat Ali, N. M. Butt
Abstract
Saleem A. Ansari, Masood Iqbal, Liaqat Ali, N. M. Butt
Abstract
The Pakistan Research Reactor was converted from 93% highly enriched uranium fuel to 20% low-enriched uranium fuel in October 1991. The reactor power was also upgraded from 5 to 9 MW. A series of critical and power experiments were performed on the new core for verification of design data and to determine the nuclear performance of the reactor. The characteristics tests included a criticality experiment, reactivity measurements on reflected and unreflected, critical and full-power cores, and flux distribution in and around the core, as well as thermal-hydraulic measurements. A comparison of the measured and the calculated results was also made. The results of the characteristics tests indicate that the performance of the new reactor is within design limits.
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The Pakistan Research Reactor was converted from 93% highly enriched uranium fuel to 20% low-enriched uranium fuel in October 1991. The reactor power was also upgraded from 5 to 9 MW. A series of critical and power experiments were performed on the new core for verification of design data and to determine the nuclear performance of the reactor. The characteristics tests included a criticality experiment, reactivity measurements on reflected and unreflected, critical and full-power cores, and flux distribution in and around the core, as well as thermal-hydraulic measurements. A comparison of the measured and the calculated results was also made. The results of the characteristics tests indicate that the performance of the new reactor is within design limits.
Key concepts: Criticality, Nuclear engineering, Enriched uranium, Uranium, Research reactor, Nuclear reactor core, Natural uranium, Thermal hydraulics