Assessing reliability of fast power reactor core operation. Part I

For simulation, the stochastic method was used. In formulating the energy balance equation for the coolant region a new boundary condition was introduced involving heat conduction in the fuel rod cans. An analysis was made of thermal and hydraulic conditions in the assembly and an uncertainty group was compiled for stochastic reliability assessment. The simulation is shown of a discrete random temperature field on the inside surface of the fuel rod cans. The application of the Monte Carlo method allowed respecting the interactions of random temperature fluctuations. (J.P.)