Abstract
Different fuel compositions have been irradiated in the BR-10, BOR-60, BN-350, and BN-600 reactors and investigated: PuO 2 , UC, UN, UPuN, UO 2 , UPuO 2 , metallic doped and undoped alloys, and fuel compositions with inert matrices. Studies of fuel elements with UPuN as well as with fuel compositions based in MgO and ZrN irradiated in the BOR-60 reactor were completed in 2009. The main results of the investigations of different fuel compositions are presented and the problems of ensuring the serviceability of BN-800 and -1200 fuel elements are discussed. Intense investigations are now being conducted in order to adopt gradually in our country’s nuclear power powergenerating units with advanced high-capacity sodium-cooled fast reactors with high safety and fuel utilization indicators. This nuclear technology has passed the commercial prototype stage and has good potential for being adopted in commercial facilities which have high safety and fuel-utilization indicators and are competitive with alternative sources of energy. At the same time, the choice of the structural characteristics of the reactor, fuel, fuel cycle, optimal fuel-utilization characteristics, and others remains open and requires additional analysis and validation.
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