Study of thermohydraulic processes in the elements of heat removal systems for advanced nuclear engineering facilities
The formulation and conduct of this work are due to: 1) unacceptable uncertainty of temperature regimes of fuel elements (fuel rods) of promising reactors in conditions close to the deteriorated heat transfer (DHT); 2) the practical impossibility of studying the temperature regimes of fuel assemblies in real conditions of nuclear reactors (NR); 3) strengthening the priority focus on passive methods of heat dissipation in nuclear energy technologies; 4) the need to increase the efficiency and reliability of promising passive heat dissipation systems of the evaporation- condensation type (ECT