Safety analysis of an accident associated with steam generator tube rupture for a nuclear power plant with WWER-440/213 reactors

The calculations included in the Operational Safety Analysis of the Dukovany NPP were repeated for new input parameters corresponding to the new fuel whose use is planned. The RELAP5 code was used. The data calculated for an accident associated with loss of coolant from the primary circuit to the secondary circuit through an equivalent hole 2 x 13.2 mm, corresponding to steam generator tube rupture, are presented. Despite some minor differences in the results, it is concluded that the time till the damaged steam generator is full is sufficiently long for operator's intervention. (P.A.). 3 tabs., 171 figs., 10 refs