SIMULATION OF A EUROPEAN PRESSURIZED REACTOR (EPR) USING THE MCNP CODE
https://doi.org/10.52676/1729-7885-2025-1-80-89
Abstract
Modeling of nuclear reactors is one of the important steps in ensuring safety and optimizing their characteristics. This work is devoted to assessing the characteristics of the core of the EPR reactor under its various operating modes in order to consider this type of reactor as a possible candidate for the construction of a nuclear power plant in Kazakhstan. The research culminated in the development of a computational model of the EPR reactor and the introduction of analytical methods to obtain additional data. The research was carried out using the Monte Carlo method developed in the MCNP program and designed to analyze in detail the neutron-physical processes occurring in the rector's core. The article presents a description of the EPR reactor, a research methodology, a computer model, simulation results and a comparison of calculated data with literature data.
About the Authors
U. A. ZhumadilovaKazakhstan
Kurchatov
I. V. Prozorova
Kazakhstan
Kurchatov
A. K. Muhamediev
Kazakhstan
Kurchatov
А. A. Prozorov
Kazakhstan
Kurchatov
Yu. A. Popov
Kazakhstan
Kurchatov
B. S. Medetbekov
Kazakhstan
Kurchatov
R. R. Sabitova
Kazakhstan
Kurchatov
S. N. Svetachev
Kurchatov
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Supplementary files
Review
For citations:
Zhumadilova U.A., Prozorova I.V., Muhamediev A.K., Prozorov А.A., Popov Yu.A., Medetbekov B.S., Sabitova R.R., Svetachev S.N. SIMULATION OF A EUROPEAN PRESSURIZED REACTOR (EPR) USING THE MCNP CODE. NNC RK Bulletin. 2025;(1):80-89. (In Russ.) https://doi.org/10.52676/1729-7885-2025-1-80-89