A Comparative Analysis of Small-Break Accidents in ISB-VVER, PSB-VVER, and VVER-1000 Reactor Installations

A comparison of three small-break accidents in integral (ISB-VVER) and full-scale (PSB-VVER) safety testing facilities and in a reactor installation, which is their prototype (VVER-1000), is presented. An analysis of the foreign and Russian literature, which considers questions of full-scale and mathematical simulation of nuclear power stations, is given. The influence of the mechanical design and the configuration of the test facilities on the way small-break accidents take place is revealed.