Radiation Physics and Engineering
A peer-reviewed journal published by K. N. Toosi University of Technology

Calculation of neutronic and kinetic parameters of Isfahan Miniature Neutron Source Reactor using slope fit and perturbation methods

Document Type : Research Article

Authors

Mahdi Ghaed Rahmati 1
Mostafa hasanzadeh 2
Seyed Amir Hossein Feghhi 3

1 Department of Nuclear Engineering, Islamic Azad University Science & Research Bosher Branch, Bosher, Iran

2 Nuclear Science and Technology

3 Reactor & Nuclear Safety School, Radiation Application Department, Nuclear Engineering Faculty, Shahid Beheshti University, Tehran, Iran

https://doi.org/10.22034/rpe.2020.104838
Abstract
Kinetic and neutronic parameters play an important role in analysis of reactors dynamic behavior. Some of these parameters include: effective multiplication factor (keff), reactivity (ρ), neutron flux as well as power spatial distributions, effective delayed neutron fraction (βeff) and prompt neutron lifetime (lp ). In this work, Monte Carlo modeling and analysis of Isfahan MNSR is performed for calculation of the kinetic and neutronic parameters of using MCNPX2.6 code, slope fit and perturbation methods. Relative differences between results of the MCNPX2.6 code in calculation of the ρ and βeff and the reference values are about 0.5% and 2.1%, respectively. The relative differences between the results of the slope fit and perturbation methods and MCNPX2.6 code in calculation of the parameter with the reference values are about 17.6%, 4.8% and 29.19%, respectively. Therefore, the results of these research show that the MCNPX2.6 code is suitable for calculation of the reactor kinetic parameters such as the βeff, while the perturbation method is a simple and convenient method for calculating the .

Highlights

  • Neutronic and kinetic parameters are calculated in Isfahan MNSR by MCNPX code.
  • These parameters play a very important role in analysis of the dynamic behavior of the reactors.
  • The slope fit and perturbation methods and MCNPX2.6 code have been used.
  • Perturbation method is a simple and convenient method for calculating the prompt neutron lifetime.

Keywords

MNSR
Neutronic and kinetic parameters
Slope fit method
Perturbation method
MCNPX2.6 code
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Radiation Physics and Engineering
Volume 1, Issue 4
Autumn 2020
Pages 1-8

  • Receive Date 05 May 2018
  • Revise Date 30 April 2019
  • Accept Date 04 February 2019

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