Experimental and recommended data base for thermophysical properties of fuel compositions for WWER reactors

Presented here is the review of content of the data base of Heat and Mass Transfer Information Center (HEMATIC, Rosatom, Russia) on thermophysical properties of fuels for the WWER-type reactors. The detailed information about data and recommendations for calculations is given for uranium dioxide and MOX-fuel (mixed uranium-plutonium oxide). Also presented is the review of information available on data and recommendations for various fuel compositions which are used as the experimental ones or are considered to be the candidates for using in experimental and/or industrial reactors - oxides, carbides and nitrides of fissile materials, their alloys and intermetal compositions, ROX-fuel and its components. (authors)