KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors

KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors

The paper considers the KIR-TG software package, which is designed for the interconnected neutron-physical and thermohydraulic test calculations of the infinite grid of VVER-SKD fuel elements. As part of the work, a software program written in the Python and Lua dynamic programming languages for lin...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) Vol. 134; no. 5-6; pp. 305 - 311
Main Authors: Belousov, V. I., Davidenko, V. D., Dyachkov, I. I., Elkin, N. N., Malkov, M. R., Ioannisian, M. V., Chernetskii, M. G., Chernitskaya, A. A., Zborovskii, V. G., Likhanskii, V. V., Khoruzhii, O. V.
Format: Journal Article
Language:English
Published: New York Springer US 01-09-2023
Springer
Springer Nature B.V
Subjects:
Approximation
Dynamic programming
Hadrons
Heat
Heavy Ions
Hydraulics
Modules
Monte Carlo method
Monte Carlo simulation
Neutron physics
Nuclear Chemistry
Nuclear Energy
Nuclear fuel elements
Nuclear Physics
Physical tests
Physics
Physics and Astronomy
Programming languages
Python
Simulation
Software
Software packages
Temperature
621.039.51
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Summary:The paper considers the KIR-TG software package, which is designed for the interconnected neutron-physical and thermohydraulic test calculations of the infinite grid of VVER-SKD fuel elements. As part of the work, a software program written in the Python and Lua dynamic programming languages for linking between the module for calculating neutron physics (KIR computer program) and the TK-SKD thermohydraulic module was created and applied. The use of precision calculation performed by the Monte Carlo method in the neutron-physical part avoids the error of deterministic approximation methods in the calculation results. The problem statement, as well as the nature and results of the work, revealed the advantages of this approach to solving problems related to thermal-hydraulic calculations: parallel neutronic and sequential thermal-hydraulic calculations do not affect the overall speed of the associated calculation, the calculation codes are developed in parallel to save time and resources, and errors are tracked separately.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-024-01059-x