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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. [ABSTRACT FROM AUTHOR]

Verification of the MRNK+KEDR-D software system being developed for calculating reactor dynamics is performed using the numerical benchmark-test PWR MOX/UO2 Transient Benchmark. The nonstationary process leading to an abrupt change of power caused by injection of large positive reactivity ~1.1 ß in 0.1 sec is studied. Analysis and a comparison of the obtained results with similar calculations performed using different software showed that the compared parameters are in agreement with one another to within admissible deviations. [ABSTRACT FROM AUTHOR]