Programs and methods for testing in the MIR research reactor fuel elements of water-cooled reactors under conditions simulating transient and emergency regimes

Information is presented on programs and methods for performing in the MIR research reactor loop tests in order to study the serviceability of the fuel elements of the water-cooled reactors in transient and emergency regimes (abrupt increase and cyclic change of power, anticipated reactivity accident and lossof-coolant accident). The characteristics of loop facilities and their instrumentation are presented. Experimental data confirming that the required test regimes were in fact attained are presented.