Journal of Nuclear Energy Science & Power Generation TechnologyISSN: 2325-9809

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Research Article, J Nucl Ene Sci Power Generat Technol Vol: 6 Issue: 1

Burn up Effects on Kinetic Parameter’s Variations in an Electron Accelerator Driven Subcritical Reactor

Ebrahimkhani M1, Hassanzadeh M2*, Feghhi SAH3 and Rahbari K1
1Department of Engineering, Science and Research Branch, Islamic Azad University, Bushehr, Iran
2Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
3Department of Nuclear Engineering, ShahidBeheshti University, G.C, Tehran, Iran
Corresponding author : Mostafa Hassanzadeh
Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
E-mail: [email protected]
Received: July 26, 2016 Accepted: January 25, 2017 Published: February 01, 2017
Citation: Ebrahimkhani M, Hassanzadeh M, Feghhi SAH, Rahbari K (2017) Burn up Effects on Kinetic Parameter’s Variations in an Electron Accelerator Driven Subcritical Reactor. J Nucl Ene Sci Power Generat Technol 6:1. doi: 10.4172/2325-9809.1000166

Abstract

One of the key components in nuclear reactors is calculation of the neutronic parameters and the burnup effect on the variation of these parameters. In this study, neutronic parameters such as neutron flux and power distributions, effective multiplication factor (Keff), neutron mean generation time (Λ), effective delayed neutron fraction (βeff) and fuel burn up are calculated in an Accelerator Driven Subcritical ALMR reactor to transmutation of TRUs by MCNPX code for the parabolic spatial distribution of electron beam. The results this study shows that with increasing in the fuel burn up the values of Keff and TRU decrease while the fission products rate increase. In addition, it observes that in comparison with the beginning-of-cycle (BOC) values, at end-of-cycle (EOC), the Λ parameter increases but the βeff parameter more or less constant as a function of burn up in the multiplication factor of 0.93. Also, according to the results, the average relative difference between the results of calculations with reference data is within 3%.

Keywords: TRU; Burn up, Kinetic parameters; Neutronic parameters; MCNPX code; ALMR reactor

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