Transient behavior during reactivity insertion in the Moroccan TRIGA Mark II reactor using the PARET/ANL code

• PARET model for the Moroccan TRIGA MARK II reactor has been developed.
• Transient behavior under reactivity insertion has been studied based on PARET code.
• Power factors required by PARET code have been calculated by using MCNP5 code.
• The dependence on time of the main thermal-hydraulic parameters was calculated.
• Results are largely far to compromise the thermal design limits.

A three dimensional model for the Moroccan 2 MW TRIGA MARK II reactor has been developed for thermal-hydraulic and safety analysis by using the PARET/ANL and MCNP5 codes. This reactor is located at the nuclear studies center of Mâamora (CENM), Morocco. The model has been validated through temperature measurements inside two instrumented fuel elements located near the center of the core, at various power levels, and also through the power and fuel temperature evolution after the reactor shutdown (SCRAM). The axial distributions of power factors required by the PARET code have been calculated in each fuel element rod by using MCNP5 code. Based on this thermal-hydraulic model, a safety analysis under the reactivity insertion phenomenon has been carried out and the dependence on time of the main thermal-hydraulic parameters was calculated. Results were compared to the thermal design limits imposed to maintain the integrity of the clad.