FRG activities with PWR advanced reactor

Design peculiarities of advanced APWR reactors as applied to the FRG conditions are considered. Pu-U mixed oxide fuel will be used in the reactor core and light water - as moderator and coolant. It is supposed that when modifying PWR reactor into APWR, the core and control system elements will be subject to substitution while steam generators, turbines, pumps and the reactor vessel will remain without changes. Joint utilization of PWR and APWR reactor will make it possible to increase the amount of electric power generated two-fold. The total electric power generation may be still increased two-fold, if one uses depleted uranium in APWR. Despite all the advantages, however, APWR is unlikely to be widely used due to a relatively high cost of electric power, generated at APWR units. This is conditioned in particular, by a high initial Pu loading (6-7 t) and a complicated fuel cycle. Therefore APWR building and operation will be justified if cost for uranium increase considerably and if fast reactors are comissioned with a considerable delay