Calculational studies of transients and emergency regimes during fast reactor operation and their role in safety assurance.


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. Bagdasarov,-Yu.E.; Kuznetsov,-I.A.