No abstract available

[en] Design and heat transfer flowsheet of NPPs with fast reactors, peculiarities of transition processes in fast reactors with liquid-metal cooling, are described. Accidental failures of systems and equipment of NPPs, the tasks of reactor accidental protection under such conditions are considered. Data on possibilities of fast reactor accidental protection in the cases of deviations of different inlet parameters, are presented. Protective system testings which are conducted during start-up and operation of NPPs are described

No abstract available

No abstract available

[en] Methods for calculation of transients in nuclear power plants with fast reactors and practical applications of these calculations are reviewed. Calculation of the reactor core, heat exchanger, pipeline and mixing chamber dynamics is considered. The ways of calculational result application for determination of the necessary parameters of emergency protection and operational restrictions are considered. Methods for solving the problem of thermal shock in fast reactors, difficulties in emergency cooling and the ways of their overcoming are described

[en] The possibility to simplify the form of solution of the system of mass transfer differential equations describing the process of radioactive particle buildup in a nuclear reactor circuit is investigated. To solve the problem the results obtained in thermal physics where simplification and unification of finite dependences are realized for analogous heat transfer equations are used. The solution of radioactive mass transfer equation for a homogeneous circuit is considered. It is pointed out that in the case of an inhomogeneous circuit the problem is to be solved similarly for separate quasihomogeneous sections into which the circuit is divided

No abstract available

No abstract available

No abstract available

[en] For the purpose of elaboration of the plan of activities on staff and population protection the consequencies of maximum hypotheti cal accident in the LMFBR type reactor core are analyzed. The consequences of accidents with main circulating pumps failures followed by the emergency protection system failure are considered. The influence of physical and thermophysical reactor parameters on maximum temperature variations in it is analyzed. A possibility of decreasing the reactor power under self-regulating conditions due to negative reactiviy effects and transition into the regime of the coolant natural circulation without its boiling in the core is discussed. A conclusion is drawn on the necessity of introducing in the plant with fast reactors the duplicating emergency protection system designed on different physical principle than the basic one. The efficiency of such system may be selected at the level of (0.2-0.5)x10^-₂