Patent Number: 
Section: claims

1. A process for demonstrating parameters required for licensure of components for use in a nuclear reactor comprising:preparing a computer generated atomistic model of at least one physical property of a component and a computer generated model predicting the behavior of the component under conditions of interest in the operation of a nuclear reactor;preparing and submitting a preliminary application for license of the component to a regulatory body responsible for approval of use of the component in a nuclear reactor based on the computer generated physical property and behavior models;placing at least one component samples in a nuclear reactor;placing sensors in the nuclear reactor to monitor parameters of interest during operation of the nuclear reactor;operating the nuclear reactor for a predetermined reactor cycle time;retrieving data from the sensors in the reactor in real time during the cycle time for instantaneous analysis of the parameters of interest;comparing the real-time data to the physical property and component behavior models;applying the compared real-time data and physical property and component behavior models to (i) validate the models and component predictions based on the models when the retrieved real-time data conforms to the model predictions, or (ii) adjusting the computer generated models and component predictions to incorporate and conform to the retrieved real-time data during and prior to completion of the reactor cycle time when the retrieved real-time data does not conform to the model predictions;when adjusted computer generated models and component predictions are generated, repeating the data retrieving, comparing real-time data and using the compared real-time data steps during the cycle time until the models and component behavior predictions are validated;communicating with the regulatory body to advance and complete the application for license of the component during and prior to completion of the cycle time based on the validated real-time data and physical property and component behavior models. 2. The process recited in claim 1 wherein the component is nuclear fuel. 3. The process recited in claim 1 wherein the component is a safety related component in a nuclear power plant. 4. The process recited in claim 1 wherein the parameters of interest are selected from the group consisting of pressure, temperature, change in component volume, stress and strain tension, energy, heat capacities, thermal conductivity, fission gas release, fuel swelling, fuel melting point, and combinations thereof. 5. The process recited in claim 1 wherein the conditions of interest in the operation of a nuclear reactor are selected from normal and accident conditions and combinations thereof. 6. The process recited in claim 1 wherein the sensors are selected from the group consisting of thermocouples, thereto-acoustic sensors, vacuum micro-electronic devices, spark gap transmitters, strain gauges, motion sensors, melting point sensors, neutron flux sensors, power sensors, and combinations thereof.