Safety analysis and optimization of the core fuel reloading for the Moroccan TRIGA Mark-II reactor

Calculation of kinetic parameters of the Moroccan TRIGA mark-II reactor using the Monte Carlo code MCNP

“…In this work, the MCNP calculated value of the effective delayed neutron fraction (βeff) for TRIGA Mark-II reactor of Morocco is about of 0.00742, as shown in Table 2. In addition, the βeff value in the principal design data for 2 MW TRIGA MARK-II reactor of Morocco equals 0.00730 [2]. There is a good agreement with the calculated value of βeff and the reference value which was mentioned above (0.00730).…”

“…Also, the safety analysis and optimization of the core fuel when the reactor is working with a power around 2 MW was established [2].…”

Fuel reloads optimization for TRIGA research reactor using Genetic Algorithm coupled with neutronic and thermal-hydraulic codes

“…These constraints define boundary regions of feasible solutions of the problem. For the TRIGA Mark II reactor, CFT and DNBR must always be lower than 750 ºC and higher than 1.3, respectively (Nacir et al, 2014).…”

“…These numerical models have been used to investigate the 131 I production feasibility by the CENM research reactor (El Bakkari et al, 2015) and to study the enhancement of radioisotope production by creating a new irradiation channel inside the reactor core (Chham et al, 2016). In addition, Nacir et al, (2014) studied the reloading of one fresh fuel element (12% wt of uranium) into the core in zero-burnup condition.…”

Effect of graphite reflector on the neutronic parameters of the TRIGA Mark II research reactor

“…A three-dimensional model of the TRIGA reactor was elaborated using the Monte Carlo code MCNP5, Some practical calculations of the neutronic safety parameters of the Moroccan TRIGA such as core excess reactivity, total and integral control rods worth and power peaking analysis were performed on the one hand, and the burnup simulation was established by using an internally developed burnup code called BUCAL1 on the other hand [2], [3]. Also, the safety analysis and optimization of the core fuel when the reactor is working with a power around 2 MW was established [4]. In this work, the most important neutronic parameter such as effective multiplication factor (Keff) was calculated as function of the number of reflector pins in core.…”