Nuclear Technology and Energy

Simulation and investigation of neutronic parameters of Tehran research reactor core using probabilistic codes

10.52547/nucte.2021.223772.1015

Articles in Press, Accepted Manuscript
Available Online from 30 May 2023
Nuclear Technology and Energy

Authors

Saeed Zare Ganjaroodi 1
Ehsan Zarifi 2
Hossein Khameh 3
nazanin zahra raei 3

1 Energy and Physics Department, Amirkabir University of Technology, 424 Hafez Ave., Tehran, Iran

2 Reactor and Nuclear Safety Research school, Nuclear Science and Technology Research Institute, Tehran, Iran

3 Faculty of Engineering Science and Research Branch, Islamic Azad university, Tehran, Iran

Abstract
The purpose of this study is to simulate and perform neutronic calculations of the Tehran Research Reactor (TRR) core using SuperMC3.2.0 and MCNPX2.7.0 monte carlo codes. Tehran research reactor is a pool and inhomogeneous type reactor and its maximum designed power is 5 MWth. Light water is used as coolant, moderator and biological shields. In this paper, due to the many advantages of the advanced and new SuperMC code including simplicity of modeling, high accuracy of calculations and access to various and complete libraries, some neutronic parameters of the core such as K-factor, excess reactivity, neutron flux, and integral and differential worth of control rods were obtained by the SuperMC and MCNPX codes. Finally, the results were benchmarked to the SAR reactor to determine the accuracy of the calculations and the importance of using the new SuperMC code. Results illustrated, in normal operation, the reactor core has an excess reactivity equal to about 65 (mK). Also, the results in the calculation of neutronic parameters between MCNPX and SuperMC codes have been compared with SAR data, the difference of which can be the error in the simulation or the difference between the libraries used in the simulation.

Keywords

Probability codes
Neutronic parameters
Tehran reactor core
Subjects

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