System and method for continuous optimization of control-variables during operation of a nuclear reactor

Abstract

A system and method is provided for a continual updating of the optimization of multiple operational control-variables during the operation of a nuclear reactor over a plurality of fuel cycles. A networked computer system includes one or more hosts programmed to execute an optimization process to identify and make changes in quantitative values of operational control-variables that result in improved efficiency and operational flexibility. Optimization and updating of operational control-variables may proceed selectively under manual control for inputting specific optimization constraints and reactor state-point information or may proceed autonomously through a repetitive performing of the optimization process based upon a predetermined user-defined strategy stored on the network. Communications between users and networked processors is facilitated by use of a TCP/IP server connected to the Internet so that portions of the optimization process may be conducted contemporaneously at remote locations and/or the results made accessible to users via conventional browser enabled computers.

1 . A method for determining and updating a projected strategy for maintaining optimal operations of a nuclear reactor based on one or more optimization input parameters and/or reactor state-point information stored in a database, comprising the steps performed by a computer or computer network of: 
 a) accepting input data for initializing or modifying one or more optimization input parameter values which collectively define a particular reactor operation strategy;    b) computing optimized quantitative values for a plurality of reactor core operational control-variables based on current reactor plant state-point data, wherein the computed optimized quantitative values meet predetermined design constraints for the reactor; and    c) displaying, on a display device coupled to said computer or computer network, at least one or more of said computed optimized quantitative control-variable values, said information being indicative of a projected strategy for optimal reactor performance.    
     
     
         2 . The method of  claim 1  further including the step of computing optimal reactor simulation results based on optimized quantitative values computed in step (b).  
     
     
         3 . The method of  claim 1  wherein the step of computing optimized quantitative values for a plurality of reactor core operational control-variables further comprises computing polynomial response surface data based on a plurality of reactor core operation simulations.  
     
     
         4 . The method of  claim 1  wherein the step of computing optimized quantitative values for a plurality of reactor core operational control-variables further comprises using predetermined polynomial response surface data to predict optimal changes in independent control-variable values, said polynomial response surface data based on a plurality of reactor core operation simulations.  
     
     
         5 . The method of  claim 1  further including the step of periodically computing updated values for one or more optimization inputs in accordance with a current time and/or a time remaining in a current fuel cycle.  
     
     
         6 . The method of  claim 1  wherein optimization input data of step (a) comprises predetermined stored optimization input parameter values which collectively define a preferred operational strategy.  
     
     
         7 . The method of  claim 6  wherein a stored reactor operational strategy incorporates reactor plant licensing requirements.  
     
     
         8 . The method of  claim 1  wherein optimization input data of step (a) is automatically retrieved from a database of optimization input data.  
     
     
         9 . The method of  claim 1  wherein optimization input data of step (a) is manually input by a user.  
     
     
         10 . The method of  claim 1  further including the step of selectively displaying historical and/or current reactor plant performance data.  
     
     
         11 . The method of  claim 1  wherein computation of optimized control-variables is performed in response to changes made to an existing or preferred reactor operational strategy.  
     
     
         12 . The method of  claim 1  further including the step of converting thermal and/or reactivity margin data into fuel cycle energy data.  
     
     
         13 . The method of  claim 1  further including the step of converting reactor fuel cycle energy data into thermal and/or reactivity margin data for subsequent display via graphical user interface.  
     
     
         14 . The method of  claim 1  wherein computing optimized quantitative values for one or more reactor core operational control-variables is performed in response to poor or inadequate process computer and/or design simulator predictions.  
     
     
         15 . The method of  claim 1  wherein computing optimized quantitative values for one or more reactor core operational control-variables is performed for a reactor during a given fuel cycle, N, so as to improve efficiency of reactor operations for a subsequent fuel cycle, N+1.  
     
     
         16 . The method of  claim 1  wherein the step of computing optimized quantitative values for one or more reactor core operational control-variables is performed and/or an optimal projected reactor operational strategy is displayed in direct response to one or more specific commands input via graphical user interface.  
     
     
         17 . The method of  claim 1  wherein the step of computing optimized quantitative values includes displaying all independent control variables via graphical user interface.  
     
     
         18 . The method of  claim 1  wherein the step of computing optimized quantitative values includes utilizing exposure dependent constraints.  
     
     
         19 . The method of  claim 1  wherein the step of computing optimized quantitative values includes providing multiple solutions from varying constraint criteria.  
     
     
         20 . The method of  claim 1  wherein the step of computing optimized quantitative values includes performing computations based upon a user selected extended reactor fuel cycle duration value.  
     
     
         21 . The method of  claim 1  further including the step of computing a maximum fuel cycle energy corresponding to a particular reduced coolant flow capability.  
     
     
         22 . The method of  claim 1  further including the step of performing a coastdown reduction computation.  
     
     
         23 . The method of  claim 1  further including the step of computing a maximum undisturbed sequence length.  
     
     
         24 . A nuclear reactor operations optimization system for determining and updating one or more strategies for optimal operations of a nuclear reactor plant based on one or more optimization input parameters and/or reactor state-point information stored in a database, comprising: 
 a plurality of optimization system host processors coupled via a digital communications network, at least one or more of said host processors operative as a control-variable optimization engine and at least one or more of said host processors providing a graphic user interface for selecting optimization inputs and inputting associated parameter values and/or displaying information indicative of an optimized operational strategy based on optimization output results provided by the optimization engine; and    a database storage device accessible by one or more of said host processors via the communications network for storage of optimization inputs and parameter values.    
     
     
         25 . The reactor operations optimization system of  claim 24  wherein at least one or more of said host processors process one or more reactor core operation simulation cases corresponding to a predetermined set of independent control-variable values.  
     
     
         26 . The reactor operations optimization system of  claim 24  wherein reactor state-point information is produced by a reactor simulation process performed by one or more of processors connected to the network and is stored in a database accessible via the communications network.  
     
     
         27 . The system of  claim 24  wherein the communications network comprises a LAN.  
     
     
         28 . The system of  claim 24  wherein the communications network comprises a WAN.  
     
     
         29 . The system of  claim 24  wherein the communications network comprises, at least in part, existing Internet communications infrastructure.  
     
     
         30 . The system of  claim 24  wherein the display device includes a graphical user interface that enables retrieval and selective display of historical and/or current reactor plant performance data stored on one or more storage devices accessible via the communications network.