Full-scale controlled transient heat-transfer tests data-analysis report

Transient critical heat flux (CHF) behavior was studied under conditions typical of those calculated to occur in the first few seconds following a postulated large break loss of coolant accident (LOCA) in a pressurized water reactor (PWR). The axial power profile was a chopped cosine with a 1.66 peak to average power ratio. The primary focus was to obtain a data base, for transient CHF in a rod bundle cooled by water, amenable to model development efforts. A single controlled parameter variation approach was utilized. The parameters variation included pressure, pressure decay rate, flow, flow decay rate, flow direction, power, inlet temperature, and initial system pressure. These parameters are selected to bound the values which are calculated to occur during a large break PWR LOCA.