Development of a new computational support tool for experiments in the impulse graphite reactor
Irkimbekov R.A. Vityuk V.A. Vityuk G.A. Zhanbolatov O.M. Surayev A.S. Popov Y.A. Kotlyar A.N.
November 2025Elsevier Ltd
Nuclear Engineering and Design
2025#443
The Impulse Graphite Reactor (IGR) is a unique nuclear reactor of the heat-capacity type. Safety issues related to reactor installations have been studied for many years using this IGR. The aim of this work is to develop a new tool for computational support during the stages involved in preparing and conducting experiments at the IGR. The tool includes neutronic and thermal models of the IGR core designed for the MCNP and Ansys Mechanical APDL programs and software developed in Visual Basic (VB.Net) environment and can be used to exchange data between models and to control model parameters. The developed models and software offer advantages over previous models, improve modeling quality, and prove crucial for performing calculations to justify experimental work on the IGR. The tool is validated using IGR experiment results. Neutron-physical and thermal parameters of the reactor are investigated, considering their mutual influence in different modes. Validation results of independent parameters, such as the neutron field in experimental channels and reactivity and thermal state of the core, show consistency with experimental data.
ANSYS , High-fidelity modeling , IGR , MCNP , Research reactors , Validation
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