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

Document Type: Original Article

Authors

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

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