Abstract
The paper presents main technical characteristics of the Impulse Graphite Reactor (IGR), which determine its unique experimental opportunities to research behavior of the fuel rods and fuel assemblies in transient and accident operation conditions. A brief review of main experimental programs implemented at the IGR in support of safety of various nuclear reactor operation was conducted. Obtained results became new and unique ones in many aspects and enabled determining important fuel rod parameters from the reactor safety and performance point of view, data on interaction process between core material melt and coolant, as well as on its controlled moving throughout special channels. The gained experience and competency of the personnel, developed methodological approaches to tests, technical equipping of the reactor allow now successfully implement new experimental programs, manage actual scientific issues and expand international cooperation in enhancing nuclear power safety.
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