Patent Document ID: 20120185222
Application ID: 13303188
Patent Flag: 0

Claim One:
1. A computational system for performing a safety analysis of a postulated Loss of Coolant Accident in a nuclear reactor, comprising: an input model which includes noding for a full spectrum of break sizes of the postulated Loss of Coolant Accident, said input model includes an input deck which identifies parameters of the nuclear reactor selected from the group consisting of reactor geometry, initial conditions and boundary conditions, said parameters include constant values and uncertainty values; an uncertainty database including a set of uncertainty values for specific parameters identifying phenomena expected to occur during the postulated Loss of Coolant Accident, said uncertainty values including break size; an input processor to extract uncertainty values from the uncertainty data base, generate an input deck for each of the uncertainty values and execute a Loss of Coolant Accident simulation for each of the uncertainty values; and a code to compute a response of the nuclear reactor to the Loss of Coolant Accident simulation for each of the uncertainty values.