Construction of the NPP with a heavy water power reactor in Argentina

The ''Atucha-2'' heavy water reactor as well as the peculiarities of automated reactor fueling, reactor control, reactor emergency provisions, moderator cooling system, main and emergency power supplies are described. The results of the analyses of credible accidents are presented. The analysis of the credible accidents, connected with the primary coolant circuit rupture, shows that the maximum temperature in the reactor core.is always in the range of 600-1000 deg C, i. e. it does not exceed 1200 deg C, as specified all over the world to be a basis for the emergency core cooling system development. A conclusion is made that the probability of accidents at the NPP considered is less than at the analogous ones, that have been already constructred, and meets completely the requirements ascertained in Argentina