Neutronic and Safety Analysis of CAREM-25 Small Modular Reactor Using Supermc Advanced Code

Document Type : Short/Technical paper


1 Department of Physics and Energy Engineering, School of Sciences, Amirkabir University of Technolog , Tehran, Iran

2 Faculty of Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran

3 Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran


Computer simulation is crucial due to the importance of estimating various parameters of a reactor in different functions. Hence, simulation codes and programs must have high credibility to perform complex calculations. SuperMC is a powerful, accurate graphic user interface Monte Carlo method-based code to simulate and model nuclear systems due to the unique features of CAREM-25 reactor, including high efficiency, complex geometry is chosen to be modeled by SuperMC and MCNPX codes to calculate neutronic and control parameters such as multiplication factor, flux and power distribution, and control rod worth. Comparing the results of the two simulations mechanism indicates the proximity of the computed values with less than a %2 difference in neutronic parameters. Also, SuperMC results show an appropriate consistency with benchmarks and references. Consequently, SuperMC can be considered an accurate, simple, and GUI Advanced program to simulate nuclear reactors.


Main Subjects

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