Characterization of used nuclear fuel with multivariate analysis for process monitoring
This paper presents initial development of a reactor-type classifier that is used to select a reactor-specific partial least squares model to predict used nuclear fuel burnup. Nuclide activities for prototypic used fuel samples were generated in ORIGEN-ARP and used to investigate techniques to chara...
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Veröffentlicht in: | Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment Accelerators, spectrometers, detectors and associated equipment, 2014, Vol.735, p.624-632 |
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container_title | Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment |
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creator | Dayman, Kenneth J. Coble, Jamie B. Orton, Christopher R. Schwantes, Jon M. |
description | This paper presents initial development of a reactor-type classifier that is used to select a reactor-specific partial least squares model to predict used nuclear fuel burnup. Nuclide activities for prototypic used fuel samples were generated in ORIGEN-ARP and used to investigate techniques to characterize used nuclear fuel in terms of reactor type (pressurized or boiling water reactor) and burnup. A variety of reactor type classification algorithms, including k-nearest neighbors, linear and quadratic discriminant analyses, and support vector machines, were evaluated to differentiate used fuel from pressurized and boiling water reactors. Then, reactor type-specific partial least squares models were developed to predict the burnup of the fuel. Using these reactor type-specific models instead of a model trained for all light water reactors improved the accuracy of burnup predictions. The developed classification and prediction models were combined and applied to a large dataset that included eight fuel assembly designs, two of which were not used in training the models, and spanned the range of the initial 235U enrichment, cooling time, and burnup values expected of future commercial used fuel for reprocessing. Error rates were consistent across the range of considered enrichment, cooling time, and burnup values. Average absolute relative errors in burnup predictions for validation data both within and outside the training space were 0.0574% and 0.0597%, respectively. The errors seen in this work are artificially low, because the models were trained, optimized, and tested on simulated, noise-free data. However, these results indicate that the developed models may generalize well to new data and that the proposed approach constitutes a viable first step in developing a fuel characterization algorithm based on gamma spectra. |
doi_str_mv | 10.1016/j.nima.2013.09.056 |
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(PNNL), Richland, WA (United States)</creatorcontrib><description>This paper presents initial development of a reactor-type classifier that is used to select a reactor-specific partial least squares model to predict used nuclear fuel burnup. Nuclide activities for prototypic used fuel samples were generated in ORIGEN-ARP and used to investigate techniques to characterize used nuclear fuel in terms of reactor type (pressurized or boiling water reactor) and burnup. A variety of reactor type classification algorithms, including k-nearest neighbors, linear and quadratic discriminant analyses, and support vector machines, were evaluated to differentiate used fuel from pressurized and boiling water reactors. Then, reactor type-specific partial least squares models were developed to predict the burnup of the fuel. Using these reactor type-specific models instead of a model trained for all light water reactors improved the accuracy of burnup predictions. The developed classification and prediction models were combined and applied to a large dataset that included eight fuel assembly designs, two of which were not used in training the models, and spanned the range of the initial 235U enrichment, cooling time, and burnup values expected of future commercial used fuel for reprocessing. Error rates were consistent across the range of considered enrichment, cooling time, and burnup values. Average absolute relative errors in burnup predictions for validation data both within and outside the training space were 0.0574% and 0.0597%, respectively. The errors seen in this work are artificially low, because the models were trained, optimized, and tested on simulated, noise-free data. 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(PNNL), Richland, WA (United States)</creatorcontrib><title>Characterization of used nuclear fuel with multivariate analysis for process monitoring</title><title>Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment</title><description>This paper presents initial development of a reactor-type classifier that is used to select a reactor-specific partial least squares model to predict used nuclear fuel burnup. Nuclide activities for prototypic used fuel samples were generated in ORIGEN-ARP and used to investigate techniques to characterize used nuclear fuel in terms of reactor type (pressurized or boiling water reactor) and burnup. A variety of reactor type classification algorithms, including k-nearest neighbors, linear and quadratic discriminant analyses, and support vector machines, were evaluated to differentiate used fuel from pressurized and boiling water reactors. Then, reactor type-specific partial least squares models were developed to predict the burnup of the fuel. Using these reactor type-specific models instead of a model trained for all light water reactors improved the accuracy of burnup predictions. The developed classification and prediction models were combined and applied to a large dataset that included eight fuel assembly designs, two of which were not used in training the models, and spanned the range of the initial 235U enrichment, cooling time, and burnup values expected of future commercial used fuel for reprocessing. Error rates were consistent across the range of considered enrichment, cooling time, and burnup values. Average absolute relative errors in burnup predictions for validation data both within and outside the training space were 0.0574% and 0.0597%, respectively. The errors seen in this work are artificially low, because the models were trained, optimized, and tested on simulated, noise-free data. However, these results indicate that the developed models may generalize well to new data and that the proposed approach constitutes a viable first step in developing a fuel characterization algorithm based on gamma spectra.</description><subject>Algorithms</subject><subject>Errors</subject><subject>Fuel Reprocessing</subject><subject>Fuels</subject><subject>Mathematical models</subject><subject>Multi-Isotope Process Monitor</subject><subject>Nuclear engineering</subject><subject>NUCLEAR FUEL CYCLE AND FUEL MATERIALS</subject><subject>Nuclear power generation</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Process Monitoring</subject><subject>Safeguards</subject><issn>0168-9002</issn><issn>1872-9576</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2014</creationdate><recordtype>article</recordtype><recordid>eNot0E1LAzEQgOEgCtbqH_AUPHnZNZPsZjdHKX6B4EXxGNJpYlO2iSZZpf56t9S5zOVlGB5CLoHVwEDebOrgt6bmDETNVM1aeURm0He8Um0nj8lsivpKMcZPyVnOGzaN6voZeV-sTTJYbPK_pvgYaHR0zHZFw4iDNYm60Q70x5c13Y5D8d8meVMsNcEMu-wzdTHRzxTR5ky3MfgSkw8f5-TEmSHbi_89J2_3d6-Lx-r55eFpcftcoWBdqZzrewRnlo4rjlYCyGbFoVOSNX3rpAWHsFwJDigaRIccjWuWHKXgzlkp5uTqcDfm4nVGXyyuMYZgsWgAwaBvp-j6EE1_fo02F731Ge0wmGDjmDW0gikFEpop5YcUU8w5Wac_0ySbdhqY3lPrjd5T6z21ZkpP1OIP0od1Hw</recordid><startdate>2014</startdate><enddate>2014</enddate><creator>Dayman, Kenneth J.</creator><creator>Coble, Jamie B.</creator><creator>Orton, Christopher R.</creator><creator>Schwantes, Jon M.</creator><general>Elsevier</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>KR7</scope><scope>L7M</scope><scope>OTOTI</scope></search><sort><creationdate>2014</creationdate><title>Characterization of used nuclear fuel with multivariate analysis for process monitoring</title><author>Dayman, Kenneth J. ; Coble, Jamie B. ; Orton, Christopher R. ; Schwantes, Jon M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c307t-ff88c1fabf292ce61164d217960485f6e1fc1bd321c34ccfc2caf4b2c632ffe63</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2014</creationdate><topic>Algorithms</topic><topic>Errors</topic><topic>Fuel Reprocessing</topic><topic>Fuels</topic><topic>Mathematical models</topic><topic>Multi-Isotope Process Monitor</topic><topic>Nuclear engineering</topic><topic>NUCLEAR FUEL CYCLE AND FUEL MATERIALS</topic><topic>Nuclear power generation</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Process Monitoring</topic><topic>Safeguards</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Dayman, Kenneth J.</creatorcontrib><creatorcontrib>Coble, Jamie B.</creatorcontrib><creatorcontrib>Orton, Christopher R.</creatorcontrib><creatorcontrib>Schwantes, Jon M.</creatorcontrib><creatorcontrib>Pacific Northwest National Lab. (PNNL), Richland, WA (United States)</creatorcontrib><collection>CrossRef</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Aerospace Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>OSTI.GOV</collection><jtitle>Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Dayman, Kenneth J.</au><au>Coble, Jamie B.</au><au>Orton, Christopher R.</au><au>Schwantes, Jon M.</au><aucorp>Pacific Northwest National Lab. (PNNL), Richland, WA (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Characterization of used nuclear fuel with multivariate analysis for process monitoring</atitle><jtitle>Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment</jtitle><date>2014</date><risdate>2014</risdate><volume>735</volume><spage>624</spage><epage>632</epage><pages>624-632</pages><issn>0168-9002</issn><eissn>1872-9576</eissn><abstract>This paper presents initial development of a reactor-type classifier that is used to select a reactor-specific partial least squares model to predict used nuclear fuel burnup. Nuclide activities for prototypic used fuel samples were generated in ORIGEN-ARP and used to investigate techniques to characterize used nuclear fuel in terms of reactor type (pressurized or boiling water reactor) and burnup. A variety of reactor type classification algorithms, including k-nearest neighbors, linear and quadratic discriminant analyses, and support vector machines, were evaluated to differentiate used fuel from pressurized and boiling water reactors. Then, reactor type-specific partial least squares models were developed to predict the burnup of the fuel. Using these reactor type-specific models instead of a model trained for all light water reactors improved the accuracy of burnup predictions. The developed classification and prediction models were combined and applied to a large dataset that included eight fuel assembly designs, two of which were not used in training the models, and spanned the range of the initial 235U enrichment, cooling time, and burnup values expected of future commercial used fuel for reprocessing. Error rates were consistent across the range of considered enrichment, cooling time, and burnup values. 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subjects | Algorithms Errors Fuel Reprocessing Fuels Mathematical models Multi-Isotope Process Monitor Nuclear engineering NUCLEAR FUEL CYCLE AND FUEL MATERIALS Nuclear power generation Nuclear reactor components Nuclear reactors Process Monitoring Safeguards |
title | Characterization of used nuclear fuel with multivariate analysis for process monitoring |
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