Regular meeting of Section 2 of the Rostechnadzor Expert Council on Validation of Computer Codes took place on November 3, 2018

Regular meeting of Section 2 of the Rostechnadzor Expert Council on Validation of Computer Codes took place on November 3, 2018. 43 specialists took part in the meeting including authorized representatives of JSC “AKME-engineering”, JSC “SSC RIAR”, JSC “Atomenergoproekt”, JSC “NIKIET”, JSC “ATOMPROEKT”, JSC “OKBM Afrikantov”, National Research Center «Kurchatov Institute», JSC OKB “GIDROPRESS”, JSC «EREC», Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN), FSUE “Aleksandrov Scientific and Research Technological Centre”, Private Institution “Innovation and Technology Centre of the “Proryv” Project”, JSC “Rusatom Service”, JSC “VNIIAES”, FSUE “Russian Federal Nuclear Center – VNIIEF”.

Results of the review of 5 computer codes were discussed at the meeting. The following codes were recommended for validation:

• “STAR-CMM+” CFD-class code verified at JSC “VNIIAES” for calculation of coolant turbulent flows and heat exchange with solid components of nuclear installations equipment under forced and/or free convection caused by temperature non-uniformity and/or volumetric heat generation;
• “CONV-3D/V2.3” CFD-class code developed by IBRAE RAN for calculation of laminary flow and turbulent stationary and non-stationary flows of coolant and heat exchange with solid components of nuclear installations equipment under forced and/or free convection caused by temperature non-uniformity and/or volumetric heat generation;
• “EVKLID/V1.2” code developed for simulation of neutronic, thermohydraulic and thermomechanical processes of the reactors with liquid-metal coolant;
• “PUCHOK-JMT” code developed by JSC “NIKIET” for thermohydraulic calculation of fuel assemblies of the fast-neutron reactors under stationary flow of liquid-metal coolant.

In relation to the “DINAR” code developed by JSC “NIKIET” for simulation of stationary condition, transient and emergency condition in fast-neutron reactors with liquid-metal coolant, it was decided to complete the review, and the recommendations on finalization of a verification report were given.

Besides, “MASKA-LM 2.0” computer code developed by JSC “State Scientific Centre of the Russian Federation – Leipunsky Institute of Physics and Power Engineering” for calculation of three-dimensional non-stationary processes of mass transfer and impurity components interaction in lead coolant of fast neutron reactors was accepted for review.