Monte Carlo modelling of TRIGA research reactor

Bakkari, B. El; Nacir, B.; Bardouni, T. El; Younoussi, C. El; Merroun, Ossama; Htet, A.; Boulaich, Y.; Zoubair, M.; Boukhal, H.; Chakir, E.

doi:10.1016/j.radphyschem.2010.04.016

Cited by 30 publications

(11 citation statements)

References 15 publications

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“…Using the heat transfer equation based on the three heat transfer modes, the thermal study Molybdenum-99 production by irradiation of the target in the central thimble showed that the materials of the temperatures do not exceed their corresponding melting points, and as was confirmed by the Figure shown in Figure 2 [22][23][24] .…”

Section: Resultsmentioning

confidence: 78%

Toward for production of Molybdenum-99 by irradiation of MoO3 target in a neutron flux

Didi

Dadouch

Jaï

et al. 2018

Bangladesh J Med Sci

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Background: Molybdenum- 99 is a parent isotope of Technetium-99m (99mTc) as intermediate to diagnosis and radiation treatment. This production is made according to irradiation of Molybdenum-98 with thermal neutrons. The cycle comprises a complex of MoO3 or the percentage of Mo-98 is 24.13%, this compressed mixture in an irradiation capsule of aluminum; the latter is disposed in the central thimble of a nuclear reactor so that the thermal neutron flux is at a maximum in order to generate 98Mo to 99Mo by nuclear reaction of (n, γ) where the crosssection of molybdenum is (0.13 ± 0.0013) barn.Method: The purpose of this study is to validate of MoO3 target that will be used for the production of Molybdenum-99 in the central thimble irradiation position of the TRIGA Mark II research reactor at CNESTEN (Morocco National Center for Nuclear Energy, Sciences and Techniques), The thermal neutron flux used for activity calculation of Mo-99 used reactor of research TRIGA Mark-II is 3.1 1011 n/cm²s at 250 KW, 2.4E+13 n/cm2s at 1.1 MW and 3.01 1013n/cm²s at 2MW, we are using Fortran-90 code for calculate the activity.Result: The result’s finding was validated by other studies.Bangladesh Journal of Medical Science Vol.17(4) 2018 p.567-572

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Section: Resultsmentioning

confidence: 78%

Toward for production of Molybdenum-99 by irradiation of MoO3 target in a neutron flux

Didi

Dadouch

Jaï

et al. 2018

Bangladesh J Med Sci

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“…The power behavior of the reactor is either specified as a function of time or is determined through a numerical solution of the point kinetics equation based on an initial steady state power corresponding to the reactor state before transient mode. The local power factors distribution needed as input parameters for PARET code were calculated in each fuel element of the core based on the MCNP5 code model of the Moroccan TRIGA MARK II reactor (El Bakkari et al, 2010).…”

Section: Methodsmentioning

confidence: 99%

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

Boulaich

Nacir

Bardouni

et al. 2015

Nuclear Engineering and Design

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“…The H/Zr atom ratio is approximately 1.65. The fuel element structure of the TRIGA Mark-II reactor is described in Fig.1, and the Physical properties of fuel and fuel follower elements are presented in Table.1 [1]. Table 1.…”

Section: Simulation Of the Moroccan Triga Reactormentioning

confidence: 99%

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

Mghar¹,

Chetaine²,

Darif³

2015

aap

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In reactor physics calculations, the measurement of kinetic parameters has an important influence on control and safety analysis of a nuclear reactor. The most important kinetic parameters of nuclear reactors are the effective delayed neutron fraction (βeff), the prompt removal lifetime (τ r) and the mean neutron generation time (Λ). In this study, the kinetic parameters of the Moroccan TRIGA Mark-II reactor were calculated using the 3-D continuous-energy Monte Carlo code MCNP5. The geometrical structure of the Moroccan reactor core and the fuel configuration were designed. The MCNP Results of these parameters are analyzed and compared with references data.

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Monte Carlo modelling of TRIGA research reactor

Cited by 30 publications

References 15 publications

Toward for production of Molybdenum-99 by irradiation of MoO3 target in a neutron flux

Toward for production of Molybdenum-99 by irradiation of MoO3 target in a neutron flux

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

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

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