EDN: HRSLIS
Authors & Affiliations
Tomashchik D.Yu.
Nuclear Safety Institute, Russian Academy of Sciences, Moscow, Russia
Tomashchik D.Yu. – Senior Researcher. Contacts: 52, Bolshaya Tulskaya st., Moscow, 115191, Russia. Tel.: +7 (495) 955-22-73; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Abstract
The safety justification of a NPP is an integral part of its operating conditions. For severe accidents (SA), especially in the case of a primary coolant leak, the pressure in the containment largely determines the dynamics of uncovering and overheating of the core, the conditions of claddings failure and the subsequent release of radioactive substances. In Russia, the SOKRAT code has been developed for modeling SA at NPPs with VVER reactors. The CONT_TH module as part of the SOKRAT code is certified for calculating the pressure, temperature and composition of the gases in the multi-compartment containments. The model content of CONT_TH, which relates to codes with lumped parameters (LP), allows one to describe such processes as the destruction of stratified layers due to buoyancy and momentum, and to describe the operation of existing and future passive safety systems. For low-power nuclear power plants (LPNP), the module includes accounting for flooding of part of the compartments with water and calculation of gas phase parameters at pressures above 10 bar. The paper provides a description of the most important models of the module, and compares the calculated data with experimental data of CFD quality and calculations using CFD and LP codes for a series of 5 tests on the PANDA facility. The module is used for deterministic calculations in support for PSA-2.
Keywords
pressure, temperature, mole fraction, hydrogen, stratification, integral codes, severe accident, SOKRAT, containment, VVER, PSA-2
Article Text (PDF, in Russian)
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Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, 1:14
