Principles of construction and development of an automatic protection system for steam generators of fast reactors

Abstract

On the example of domestic fast reactors BN-350, BN-600, BN-800, the evolution of technical solutions for the automatic protection system of sodium-water steam generators (SG APS) is analyzed. The structural diagrams and main characteristics of the SG APS equipment of listed reactors are presented. The effectiveness of the SG APS in conditions of real leaks in steam generators of BN reactors is analyzed. The issues of development and creation of the SG APS of designed BN-1200 and INU MBIR are considered.