One of the most prominent reactor safety research facilities in the world was the Loss-of-Fluid Test (LOFT) facility, located at the Idaho National Engineering Laboratory. This unique facility was a 50-MW(th) pressurized water reactor designed on the principle of volume scaling to simulate the major components and system responses of a four-loop commercial pressurized water reactor during a hypothetical loss-of-coolant accident. Extensive research programs were conducted at the LOFT facility under the sponsorship of the United States Nuclear Regulatory Commission and later under the auspices of the Organization for Economic Cooperation and Development (OECD) with funding from a consortium of ten countries.
Forty-four experiments were completed over a nine year period ending with a severe fuel damage experiment in July 1985. These experiments were conducted at typical initial and boundary conditions associated with loss-of-coolant accidents and anticipated transients in commercial pressurized water reactors. The research program included six nuclear large break loss-of-coolant accident experiments, the primary objective of which was to obtain data on loss-of-coolant accidents phenomena and system response for a range of initial and boundary conditions which could be used for reactor system code development and assessment.
Photos c. 1974-1975