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

Mghar, Mohammed; Chetaine, Abdelouahed; Darif, Abdelaziz

doi:10.12988/aap.2015.531

Cited by 4 publications

(3 citation statements)

References 9 publications

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“…with 𝑘 𝑡 is the total multiplication factor (delayed neutron and prompt neutron), and 𝑘 𝑝 is the prompt neutron multiplication factor. Equation ( 9) is a method for finding 𝛽 𝑒𝑓𝑓 known as the prompt method, which has been utilized by Mweetwa [17], Hassanzadeh [20], Henry [21], Mghar [22], and Michalek [23], with excellent results. Thus, Λ can be obtained using Eq.…”

Section: Kinetic Parametersmentioning

confidence: 99%

“…The delayed neutron fraction is calculated by comparing the difference in the reactor's effective multiplication factor, including prompt and delayed neutrons, with the multiplication factor of the reactor regardless of the delayed neutrons. However, this method has been tested by [22] on the Moroccan TRIGA Mark II reactor with a difference of 1.65 % from the results of the direct study. The results of the prompt neutron lifetime are calculated directly by MCNPX by tracking the neutron movement one by one.…”

Section: Kinetic Parametermentioning

confidence: 99%

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Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

Nuryana,

Mahmudah,

Khakim

2023

Atom Indo.

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A novel simulation to calculate the neutronic parameters of the TRIGA 2000 reactor using plate-type fuel has been performed. The plate fuel used was produced by the Indonesian Nuclear Industry (PT INUKI) with U3Si2-Al material. Neutronic parameters based on INUKI’s plate-type fuel dimension and the current TRIGA’s configuration were simulated using MCNPX. The simulation was performed by modeling the complete reactor’s configuration on a fresh fuel core state. We obtained the kinetic parameter values from the simulation, i.e., delayed neutron fraction of 8.11×10‑3, a prompt neutron lifetime of 2.0551×10‑4 s, and an average neutron generation time of 1.87×10‑4 s. The excess reactivity of the reactor was 9.02 %Δk/k, while reactivity in the one-stuck-rod state was below ‑0.5 $ with an average value of ‑3.40 %Δk/k (‑4.19 $). The average thermal neutron flux peak occurred at the central irradiation position with the value of 3.0×1013 to 3.1×1013 n/(cm2 s). The reactor has a power peaking factor of 1.379 in the control rod position of 0 % on D3 fuel. The reactor had a negative feedback reactivity coefficient, except for the moderator coefficient. These results suggest that the current configuration of plate-type fuel met the nuclear reactor neutronic safety standards.

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Section: Kinetic Parametersmentioning

confidence: 99%

Section: Kinetic Parametermentioning

confidence: 99%

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

Nuryana,

Mahmudah,

Khakim

2023

Atom Indo.

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“…The fuel elements are a homogeneous alloy of zirconium hydride and uranium enriched at about 20% in 235 U, embedded in stainless-steel cladding. The hydrogen/zirconium atom ratio is of the order of 1.65 [4].…”

Section: Introductionmentioning

confidence: 99%

Investigation of the influence of various reflector elements material types on the core nuclear parameters of the 2 MW Triga Mark-II research reactor using the Monte Carlo code

Darif¹,

Chetaine²,

Mghar³

et al. 2018

Turk J Phys

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The influence of variation in the kind of material of neutron reflector elements on the core neutronic parameters of the Moroccan Triga Mark-II research reactor was examined. The comparison was made between three kinds of reflector element materials: graphite, beryllium, and beryllium oxide. MCNP5 Monte Carlo computations of the effective neutron multiplication factor ( k ef f ) of the reactor according to the number of reflector material elements inserted in the reactor core for these three reflector elements materials families were carried out. The results found could be used in order to increase the k ef f parameter without changing the size of the reactor.

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Utilization of Military Grade Plutonium in Generation-IV Gas Cooled Fast Reactor

Ibrahim

2021

Progress in Nuclear Energy

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

Cited by 4 publications

References 9 publications

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

Investigation of the influence of various reflector elements material types on the core nuclear parameters of the 2 MW Triga Mark-II research reactor using the Monte Carlo code

Utilization of Military Grade Plutonium in Generation-IV Gas Cooled Fast Reactor

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