PRESSURIZED WATER REACTOR TRANSIENT ANALYSIS MODEL

THIS PROPOSAL DESCRIBES A PROGRAM FOR THE DEVELOPMENT OF A PRESSURIZED WATER REACTOR (PWR) TRANSIENT ANALYSIS MODEL FOR USE ON A MICROCOMPUTER. THE INTENDED APPLICATION OF THIS PWR MODEL IS FOR ANALYSIS OF PWR SYSTEM RESPONSE, INCLUDING FORCED AND NATURAL CIRCULATION OPERATION. THE PRIMARY USER OF SUCH A MODEL WOULD BE A UTILITY OR NUCLEAR REGULATORY COMMISSION (NRC) ENGINEER OR PLANT OPERATOR PERFORMING SCOPING STUDIES OR INVESTIGATING THE RESPONSE TO THE PWR SYSTEM IN VARIOUS OPERATING MODES. THE FIRST PHASE OF THIS PROGRAM WILL INCLUDE SELECTION OF THE MICROCOMPUTER HARDWARE FOR MODEL DEVELOPMENT, CODE DESIGN OF THE PWR MODELMODULES, DEVELOPMENT OF TECHNICAL SPECIFICATIONS, IMPLEMENTATION OF THE PRIMARY COOLANT RECIRCULATION SYSTEM MODULE AND DOCUMENTATION. THE IMPLEMENTATION OF THE RECIRCULATION SYSTEM MODEL WILL BE AN IMPORTANT ELEMENT OF THE FIRST PHASE SINCE IT WILL DEMONSTRATE THE FEASIBILITY OF USING SUCH A MODEL ON A MICROCOMPUTER. THE USE OF THIS FIRST PHASE MODEL WILL BE TO PREDICT REACTOR COOLANT TEMPERATURE UNDER REDUCED FLOW CONDITIONS WHICH COULD LEAD PRESSURIZED THERMAL SHOCK. THE SECOND AND THIRD PHASES OF THE PROGRAM WILL INCLUDE IMPLEMENTATION OF ADDITIONAL PROGRAM MODULES, MODEL DEBUGGING, DEVELOPMENT OF PRE- AND POST-PROCESSORS FOR INPUT AND OUTPUT AND COMPARISON TO AVAILABLE PWR DATA.