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Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code

  • Engineering Physics
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Moscow University Physics Bulletin Aims and scope

Abstract

The aim of this work is to study the fuel depletion of 30 kW miniature neutron source reactor (MNSR). Under operating conditions of two hours per day for five days a week at a peak thermal neutron flux of 1.0E+12 n/cm2 s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing to generate the fuel group constants and the infinite multiplication factor versus the MNSR reactor operating time, at different burn-up values. The amounts of uranium burnt up and plutonium produced in the reactor core are calculated using the DRAGON5 transport lattice code. The results are in good agreement with previous studies.

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Acknowledgments

Special thanks should be given to Professor Otman El Hajjaji, my research project supervisor for his scientific and professional guidance and his valuable support and to Professor Tarek El Bardouni for his useful and constructive recommendations on this work.

Thank you also to all members of the Radiation and Nuclear Systems (RNS) laboratory.

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Authors and Affiliations

  1. Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences, Tetouan, Morocco

    Jamal Al Zain, O. El Hajjaji & T. El Bardouni

  2. Physics Department, Sana’a University, Sana’a, Yemen

    Jamal Al Zain

Authors
  1. Jamal Al Zain
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  2. O. El Hajjaji
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  3. T. El Bardouni
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Corresponding author

Correspondence to Jamal Al Zain.

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Al Zain, J., El Hajjaji, O. & El Bardouni, T. Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code. Moscow Univ. Phys. 74, 706–709 (2019). https://doi.org/10.3103/S0027134919060031

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  • DOI: https://doi.org/10.3103/S0027134919060031

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