Exxon nuclear fuel heatup model for PWR loss of coolant accidents

The Exxon Nuclear fuel heatup model for pressurized water reactor loss of coolant accidents consists of the analytical methodology, including computer codes, used to predict the fuel thermal transient which would result from a Loss of Coolant Accident (LOCA) due to a postulated pipe break in the primary coolant loop. The ENC fuel heatup model does not include the methodology used to predict the hydraulic transients following the pipe break, since those transients are established by the nuclear steam system design and operating parameters and are, in general, not significantly affected by fuel design parameters. Output from the separately-calculated blowdown and reflood analyses is used as input to the ENC fuel heatup model. (U.S.)