Аннотация
The conversion of research reactors to low-enriched uranium (LEU) fuel is assumed on the base of the National Nuclear Center of the Republic of Kazakhstan. The high-enriched uranium (HEU) fuel will be down blended up to the condition that prevents proliferation of nuclear weapons. Material testing have been carried out in order to determine the properties of non-irradiated HEU fuel important for transportation and future down blending of the fuel. Non-irradiated IGR reactor HEU fuel will be used for fuel down blending method development. LEU fuel was studied to obtain information about properties for comparison with HEU fuel. Determination of structural and phase analysis of material is one of the key point in material studies of IGR reactor fuel. Literature overview revealed the absence of technical standard documentation specifying requirements for structural specifications of graphite of uranium-graphite fuel and, correspondently, for application of X-ray structural analysis to define graphite structural specifications. The paper presents main results of material research and focused on analysis of x-ray specifications of uranium-graphite fuel. The progress report was presented at VIII International Conference “Semipalatinsk Test Site: Legacy and Prospects for Scientific and Technical Potential Development”.