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

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/cm 2 s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing...

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Veröffentlicht in:	Moscow University physics bulletin 2019-11, Vol.74 (6), p.706-709
Hauptverfasser:	Al Zain, Jamal, El Hajjaji, O., El Bardouni, T.
Format:	Artikel
Sprache:	eng
Schlagworte:	Depletion Engineering Physics Mathematical and Computational Physics Multiplication Neutron flux Neutrons Nuclear fuels Physics Physics and Astronomy Plutonium Theoretical Thermal neutrons Uranium
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