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Publication Details
AFRICAN RESEARCH NEXUS
SHINING A SPOTLIGHT ON AFRICAN RESEARCH
energy
Fuel burnup analysis for the Moroccan TRIGA research reactor
Annals of Nuclear Energy, Volume 51, Year 2013
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Description
The fundamental advantage and main reason to use Monte Carlo methods for burnup calculations is the possibility to generate extremely accurate burnup dependent one group cross-sections and neutron fluxes for arbitrary core and fuel geometries. Yet, a set of values determined for a material at a given position and time remains accurate only in a local region, in which neutron spectrum and flux vary weakly - and only for a limited period of time, during which changes of the local isotopic composition are minor. This paper presents the approach of fuel burnup evaluation used at the Moroccan TRIGA MARK II research reactor. The approach is essentially based upon the utilization of BUCAL1, an in-house developed burnup code. BUCAL1 is a FORTRAN computer code designed to aid in analysis, prediction, and optimization of fuel burnup performance in nuclear reactors. The code was developed to incorporate the neutron absorption reaction tally information generated directly by MCNP5 code in the calculation of fissioned or neutron-transmuted isotopes for multi-fueled regions. The fuel cycle length and changes in several core parameters such as: core excess reactivity, control rods position, fluxes at the irradiation positions, axial and radial power factors and other parameters are estimated. Besides, this study gives valuable insight into the behavior of the reactor and will ensure better utilization and operation of the reactor during its life-time and it will allow the establishment of strategic planning for fuel management such as shuffling and/or reloading schemes and its safe implementation. © 2012 Elsevier Ltd. All rights reserved.
Authors & Co-Authors
El Bakkari, Bilal
Morocco, Rabat
National Energy Center of Nuclear Science and Technology
Morocco, Tetouan
Faculté Des Sciences de Tétouan
El Bardouni, Tarek
Morocco, Tetouan
Faculté Des Sciences de Tétouan
Nacir, Bouzekri
Morocco, Rabat
National Energy Center of Nuclear Science and Technology
El Younoussi, Chafik
Morocco, Rabat
National Energy Center of Nuclear Science and Technology
Morocco, Tetouan
Faculté Des Sciences de Tétouan
Boulaich, Y.
Morocco, Rabat
National Energy Center of Nuclear Science and Technology
Morocco, Tetouan
Faculté Des Sciences de Tétouan
Boukhal, Hamid
Morocco, Tetouan
Faculté Des Sciences de Tétouan
Zoubair, M.
Morocco, Tetouan
Faculté Des Sciences de Tétouan
Statistics
Citations: 15
Authors: 7
Affiliations: 2
Identifiers
Doi:
10.1016/j.anucene.2012.07.030
ISSN:
03064549
Research Areas
Cancer