TY - JOUR ID - 104838 TI - Calculation of neutronic and kinetic parameters of Isfahan Miniature Neutron Source Reactor using slope fit and perturbation methods JO - Radiation Physics and Engineering JA - RPE LA - en SN - 2645-6397 AU - Ghaed Rahmati, Mahdi AU - hasanzadeh, Mostafa AU - Feghhi, Seyed Amir Hossein AD - Department of Nuclear Engineering, Islamic Azad University Science & Research Bosher Branch, Bosher, Iran AD - Nuclear Science and Technology AD - Reactor & Nuclear Safety School, Radiation Application Department, Nuclear Engineering Faculty, Shahid Beheshti University, Tehran, Iran Y1 - 2020 PY - 2020 VL - 1 IS - 4 SP - 1 EP - 8 KW - MNSR KW - Neutronic and kinetic parameters KW - Slope fit method KW - Perturbation Method KW - MCNPX2.6 code DO - 10.22034/rpe.2020.104838 N2 - 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 . UR - https://rpe.kntu.ac.ir/article_104838.html L1 - https://rpe.kntu.ac.ir/article_104838_04b418c4be9888550264485862f26ca4.pdf ER -