Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor
•MBurnup scheme with fully coupled Monte Carlo neutronics, subchannel thermalhydraulics and fuel-performance analysis.•Validation for the beginning of the first operating cycle of a Pre-Konvoi PWR plant.•Deviations between results and experimental data bellow 10 ppm for the critical boron concentrat...
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| Veröffentlicht in: | Nuclear engineering and design 2021-08, Vol.379, p.111173, Article 111173 |
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| creator | García, Manuel Bilodid, Yurii Basualdo Perello, Joaquín Tuominen, Riku Gommlich, Andre Leppänen, Jaakko Valtavirta, Ville Imke, Uwe Ferraro, Diego Van Uffelen, Paul Seidl, Marcus Sanchez-Espinoza, Victor |
| description | •MBurnup scheme with fully coupled Monte Carlo neutronics, subchannel thermalhydraulics and fuel-performance analysis.•Validation for the beginning of the first operating cycle of a Pre-Konvoi PWR plant.•Deviations between results and experimental data bellow 10 ppm for the critical boron concentration.•Pin-level neutron flux profiles in very good agreement with aeroball measurements.•Assessment of the impact of including fuel-performance capabilities.
The focus of this work is the validation of Serpent-SUBCHANFLOW-TRANSURANUS, a high-fidelity multiphysics system coupling Monte Carlo neutron transport, subchannel thermalhydraulics and fuel-performance analysis. A full-core pin-by-pin burnup calculation for the first operating cycle of a Pre-Konvoi PWR plant is presented and the results are assessed using experimental data. The critical boron concentration and a set of pin-level neutron flux profiles are compared against measurements, with very good agreement. The impact of using fuel-performance analysis is discussed comparing the results obtained with the three-code coupling with the ones using the traditional neutronic-thermalhydraulic approach. The studies presented here are part of the final stage of the EU Horizon 2020 McSAFE project, closing the development cycle of the Serpent-SUBCHANFLOW-TRANSURANUS system, from implementation to validation. |
| doi_str_mv | 10.1016/j.nucengdes.2021.111173 |
| format | Article |
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The focus of this work is the validation of Serpent-SUBCHANFLOW-TRANSURANUS, a high-fidelity multiphysics system coupling Monte Carlo neutron transport, subchannel thermalhydraulics and fuel-performance analysis. A full-core pin-by-pin burnup calculation for the first operating cycle of a Pre-Konvoi PWR plant is presented and the results are assessed using experimental data. The critical boron concentration and a set of pin-level neutron flux profiles are compared against measurements, with very good agreement. The impact of using fuel-performance analysis is discussed comparing the results obtained with the three-code coupling with the ones using the traditional neutronic-thermalhydraulic approach. The studies presented here are part of the final stage of the EU Horizon 2020 McSAFE project, closing the development cycle of the Serpent-SUBCHANFLOW-TRANSURANUS system, from implementation to validation.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2021.111173</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Boron ; Coupling ; Experimental data ; Fuel-performance analysis ; Fuels ; High-fidelity multiphysics ; Impact analysis ; Mathematical analysis ; Monte Carlo neutron transport ; Neutron flux ; Nuclear fuels ; Pin level burnup ; Pre-Konvoi PWR ; Pressurized water reactors ; Subchannel thermalhydraulics</subject><ispartof>Nuclear engineering and design, 2021-08, Vol.379, p.111173, Article 111173</ispartof><rights>2021 Elsevier B.V.</rights><rights>Copyright Elsevier BV Aug 1, 2021</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c343t-7c04992b6af9dad5d748b1e25d3257a199c5d085eabff5dff94016b25485f88a3</citedby><cites>FETCH-LOGICAL-c343t-7c04992b6af9dad5d748b1e25d3257a199c5d085eabff5dff94016b25485f88a3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.nucengdes.2021.111173$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3548,27923,27924,45994</link.rule.ids></links><search><creatorcontrib>García, Manuel</creatorcontrib><creatorcontrib>Bilodid, Yurii</creatorcontrib><creatorcontrib>Basualdo Perello, Joaquín</creatorcontrib><creatorcontrib>Tuominen, Riku</creatorcontrib><creatorcontrib>Gommlich, Andre</creatorcontrib><creatorcontrib>Leppänen, Jaakko</creatorcontrib><creatorcontrib>Valtavirta, Ville</creatorcontrib><creatorcontrib>Imke, Uwe</creatorcontrib><creatorcontrib>Ferraro, Diego</creatorcontrib><creatorcontrib>Van Uffelen, Paul</creatorcontrib><creatorcontrib>Seidl, Marcus</creatorcontrib><creatorcontrib>Sanchez-Espinoza, Victor</creatorcontrib><title>Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor</title><title>Nuclear engineering and design</title><description>•MBurnup scheme with fully coupled Monte Carlo neutronics, subchannel thermalhydraulics and fuel-performance analysis.•Validation for the beginning of the first operating cycle of a Pre-Konvoi PWR plant.•Deviations between results and experimental data bellow 10 ppm for the critical boron concentration.•Pin-level neutron flux profiles in very good agreement with aeroball measurements.•Assessment of the impact of including fuel-performance capabilities.
The focus of this work is the validation of Serpent-SUBCHANFLOW-TRANSURANUS, a high-fidelity multiphysics system coupling Monte Carlo neutron transport, subchannel thermalhydraulics and fuel-performance analysis. A full-core pin-by-pin burnup calculation for the first operating cycle of a Pre-Konvoi PWR plant is presented and the results are assessed using experimental data. The critical boron concentration and a set of pin-level neutron flux profiles are compared against measurements, with very good agreement. The impact of using fuel-performance analysis is discussed comparing the results obtained with the three-code coupling with the ones using the traditional neutronic-thermalhydraulic approach. The studies presented here are part of the final stage of the EU Horizon 2020 McSAFE project, closing the development cycle of the Serpent-SUBCHANFLOW-TRANSURANUS system, from implementation to validation.</description><subject>Boron</subject><subject>Coupling</subject><subject>Experimental data</subject><subject>Fuel-performance analysis</subject><subject>Fuels</subject><subject>High-fidelity multiphysics</subject><subject>Impact analysis</subject><subject>Mathematical analysis</subject><subject>Monte Carlo neutron transport</subject><subject>Neutron flux</subject><subject>Nuclear fuels</subject><subject>Pin level burnup</subject><subject>Pre-Konvoi PWR</subject><subject>Pressurized water reactors</subject><subject>Subchannel thermalhydraulics</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><recordid>eNqFkM1uGyEURlHVSnXTPkORusYFZsgMS8dqfhQrieK46Q4xcImwJjCFGavZ5smD4yjb3gV3892DvoPQd0bnjLLjn9t5mAyEBwt5zilnc1amqT6gGWsbThoh_3xEM0q5JKKW1Wf0Ject3Y_kM_T8W_fe6tHHgKPDa0gDhJGsNyfL88XV6er6ntzdLq7Wm_Js1njwgXRPpCzcTSlMAza6N1P_Csh4yj48YPg3QPKPhaN7XNgauxQfscY3CchlDLvo8c39LU6gzRjTV_TJ6T7Dt7d9hDanv-6W52R1fXaxXKyIqepqJI2htZS8O9ZOWm2Fbeq2Y8CFrbhoNJPSCEtbAbpzTljnZF30dFzUrXBtq6sj9OPAHVL8O0Ee1TaWDuVLVUKSVk3RU1LNIWVSzDmBU0PpotOTYlTthauteheu9sLVQXi5XBwuoZTYeUgqGw_BgPUJzKhs9P9lvADlV44E</recordid><startdate>20210801</startdate><enddate>20210801</enddate><creator>García, Manuel</creator><creator>Bilodid, Yurii</creator><creator>Basualdo Perello, Joaquín</creator><creator>Tuominen, Riku</creator><creator>Gommlich, Andre</creator><creator>Leppänen, Jaakko</creator><creator>Valtavirta, Ville</creator><creator>Imke, Uwe</creator><creator>Ferraro, Diego</creator><creator>Van Uffelen, Paul</creator><creator>Seidl, Marcus</creator><creator>Sanchez-Espinoza, Victor</creator><general>Elsevier B.V</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7ST</scope><scope>7TB</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope><scope>SOI</scope></search><sort><creationdate>20210801</creationdate><title>Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor</title><author>García, Manuel ; Bilodid, Yurii ; Basualdo Perello, Joaquín ; Tuominen, Riku ; Gommlich, Andre ; Leppänen, Jaakko ; Valtavirta, Ville ; Imke, Uwe ; Ferraro, Diego ; Van Uffelen, Paul ; Seidl, Marcus ; Sanchez-Espinoza, Victor</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c343t-7c04992b6af9dad5d748b1e25d3257a199c5d085eabff5dff94016b25485f88a3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Boron</topic><topic>Coupling</topic><topic>Experimental data</topic><topic>Fuel-performance analysis</topic><topic>Fuels</topic><topic>High-fidelity multiphysics</topic><topic>Impact analysis</topic><topic>Mathematical analysis</topic><topic>Monte Carlo neutron transport</topic><topic>Neutron flux</topic><topic>Nuclear fuels</topic><topic>Pin level burnup</topic><topic>Pre-Konvoi PWR</topic><topic>Pressurized water reactors</topic><topic>Subchannel thermalhydraulics</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>García, Manuel</creatorcontrib><creatorcontrib>Bilodid, Yurii</creatorcontrib><creatorcontrib>Basualdo Perello, Joaquín</creatorcontrib><creatorcontrib>Tuominen, Riku</creatorcontrib><creatorcontrib>Gommlich, Andre</creatorcontrib><creatorcontrib>Leppänen, Jaakko</creatorcontrib><creatorcontrib>Valtavirta, Ville</creatorcontrib><creatorcontrib>Imke, Uwe</creatorcontrib><creatorcontrib>Ferraro, Diego</creatorcontrib><creatorcontrib>Van Uffelen, Paul</creatorcontrib><creatorcontrib>Seidl, Marcus</creatorcontrib><creatorcontrib>Sanchez-Espinoza, Victor</creatorcontrib><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Environment Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Environment Abstracts</collection><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>García, Manuel</au><au>Bilodid, Yurii</au><au>Basualdo Perello, Joaquín</au><au>Tuominen, Riku</au><au>Gommlich, Andre</au><au>Leppänen, Jaakko</au><au>Valtavirta, Ville</au><au>Imke, Uwe</au><au>Ferraro, Diego</au><au>Van Uffelen, Paul</au><au>Seidl, Marcus</au><au>Sanchez-Espinoza, Victor</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor</atitle><jtitle>Nuclear engineering and design</jtitle><date>2021-08-01</date><risdate>2021</risdate><volume>379</volume><spage>111173</spage><pages>111173-</pages><artnum>111173</artnum><issn>0029-5493</issn><eissn>1872-759X</eissn><abstract>•MBurnup scheme with fully coupled Monte Carlo neutronics, subchannel thermalhydraulics and fuel-performance analysis.•Validation for the beginning of the first operating cycle of a Pre-Konvoi PWR plant.•Deviations between results and experimental data bellow 10 ppm for the critical boron concentration.•Pin-level neutron flux profiles in very good agreement with aeroball measurements.•Assessment of the impact of including fuel-performance capabilities.
The focus of this work is the validation of Serpent-SUBCHANFLOW-TRANSURANUS, a high-fidelity multiphysics system coupling Monte Carlo neutron transport, subchannel thermalhydraulics and fuel-performance analysis. A full-core pin-by-pin burnup calculation for the first operating cycle of a Pre-Konvoi PWR plant is presented and the results are assessed using experimental data. The critical boron concentration and a set of pin-level neutron flux profiles are compared against measurements, with very good agreement. The impact of using fuel-performance analysis is discussed comparing the results obtained with the three-code coupling with the ones using the traditional neutronic-thermalhydraulic approach. The studies presented here are part of the final stage of the EU Horizon 2020 McSAFE project, closing the development cycle of the Serpent-SUBCHANFLOW-TRANSURANUS system, from implementation to validation.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2021.111173</doi></addata></record> |
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| source | Elsevier ScienceDirect Journals Complete |
| subjects | Boron Coupling Experimental data Fuel-performance analysis Fuels High-fidelity multiphysics Impact analysis Mathematical analysis Monte Carlo neutron transport Neutron flux Nuclear fuels Pin level burnup Pre-Konvoi PWR Pressurized water reactors Subchannel thermalhydraulics |
| title | Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor |
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