Experimental and analytical investigations of thermal hydraulics for fast reactor core

The need to improve fast reactor performance (in particular of reactor core and intermediate heat exchangers) is a vital problem, resolution of which depends largely on the quality thermal physic validation. Features of fast reactor performance (high neutron flux, great pressure of gas fission products inside of fuel pins, high levels of fuel and pin clad temperatures), uncertainties in some parameters have resulted in a special attention to be given to in-depth analysis of thermal physic processes and investigations of a new phenomena that are adequate for the modern knowledge. Inter-channel hydrodynamic and thermal exchange, variable power production, entrance thermal region, deformation of pin bundle, non-standard geometry, thermal loads far from symmetric and availability of spacer structures, regular and stochastic temperature non-uniformity and ensuing hot spots - is far not a whole list of the problems posed recently by practice and being of a great importance in thermal physic validation of fast reactor core