Development of the triangle-based nodal algorithm for reconstructing pin power distributions
The fuel pin power is an essential parameter for increasing the safety and reliability features of the reactor. Although the high-order triangle-based polynomial expansion nodal (TPEN) algorithm had been suggested for incredible accuracy and computational speed in hexagonal core analyses, the pin po...
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description | The fuel pin power is an essential parameter for increasing the safety and reliability features of the reactor. Although the high-order triangle-based polynomial expansion nodal (TPEN) algorithm had been suggested for incredible accuracy and computational speed in hexagonal core analyses, the pin power reconstruction of this algorithm is not developed and assessed. This paper presents the characteristics and performances of the TPEN algorithm for pin power reconstruction. The converged nodal information obtained from sweep between coarse-mesh finite difference (CMFD) and TPEN methods is used to reconstruct the neutron flux distribution in a homogeneous fuel assembly. The modulation technique is used to obtain the heterogeneous distribution of power density. In this technique, the power density homogeneous distribution, calculated with the reconstructed neutron flux is multiplied by a form function. These functions are generated by DRAGON5. The results obtained by this algorithm are verified for various core configurations of a VVER-1000 reactor. The pin power factors show good agreement with the reference solution obtained by heterogeneous fine mesh finite element method. The largest and average relative errors found were of the order of 5% and 0.5% for TPEN, in a peripheral cell of a fuel element with the faces towards the region of the baffle/reflector. We also compared the results with those obtained from the nodal expansion method (NEM). The maximum and mean relative error of 10% and 1% are found by the NEM method.
•The TPEN method is used to obtain pin power distribution.•The results of the TPEN and NEM methods is assessed for pin power reconstruction.•The fine mesh finite difference method is used to obtain the reference value. |
doi_str_mv | 10.1016/j.pnucene.2020.103282 |
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•The TPEN method is used to obtain pin power distribution.•The results of the TPEN and NEM methods is assessed for pin power reconstruction.•The fine mesh finite difference method is used to obtain the reference value.</description><identifier>ISSN: 0149-1970</identifier><identifier>EISSN: 1878-4224</identifier><identifier>DOI: 10.1016/j.pnucene.2020.103282</identifier><language>eng</language><publisher>Oxford: Elsevier Ltd</publisher><subject>Algorithms ; Electric power distribution ; Finite difference method ; Finite element analysis ; Finite element method ; Form function ; Fuels ; Hexagonal core ; Mathematical analysis ; Neutron flux ; Neutrons ; Nuclear engineering ; Nuclear fuel elements ; Nuclear fuels ; Nuclear reactors ; Nuclear safety ; Pin-wise power ; Polynomials ; Probability ; Reconstruction ; Studies ; TPEN method</subject><ispartof>Progress in nuclear energy (New series), 2020-04, Vol.122, p.103282, Article 103282</ispartof><rights>2020 Elsevier Ltd</rights><rights>Copyright Elsevier BV Apr 2020</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c337t-96b619e771aed18226de71d177f5aafc5d51d7625fc8ddb7283dae2e05096d913</citedby><cites>FETCH-LOGICAL-c337t-96b619e771aed18226de71d177f5aafc5d51d7625fc8ddb7283dae2e05096d913</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.pnucene.2020.103282$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3550,27924,27925,45995</link.rule.ids></links><search><creatorcontrib>Safarzadeh, Omid</creatorcontrib><title>Development of the triangle-based nodal algorithm for reconstructing pin power distributions</title><title>Progress in nuclear energy (New series)</title><description>The fuel pin power is an essential parameter for increasing the safety and reliability features of the reactor. Although the high-order triangle-based polynomial expansion nodal (TPEN) algorithm had been suggested for incredible accuracy and computational speed in hexagonal core analyses, the pin power reconstruction of this algorithm is not developed and assessed. This paper presents the characteristics and performances of the TPEN algorithm for pin power reconstruction. The converged nodal information obtained from sweep between coarse-mesh finite difference (CMFD) and TPEN methods is used to reconstruct the neutron flux distribution in a homogeneous fuel assembly. The modulation technique is used to obtain the heterogeneous distribution of power density. In this technique, the power density homogeneous distribution, calculated with the reconstructed neutron flux is multiplied by a form function. These functions are generated by DRAGON5. The results obtained by this algorithm are verified for various core configurations of a VVER-1000 reactor. The pin power factors show good agreement with the reference solution obtained by heterogeneous fine mesh finite element method. The largest and average relative errors found were of the order of 5% and 0.5% for TPEN, in a peripheral cell of a fuel element with the faces towards the region of the baffle/reflector. We also compared the results with those obtained from the nodal expansion method (NEM). The maximum and mean relative error of 10% and 1% are found by the NEM method.
•The TPEN method is used to obtain pin power distribution.•The results of the TPEN and NEM methods is assessed for pin power reconstruction.•The fine mesh finite difference method is used to obtain the reference value.</description><subject>Algorithms</subject><subject>Electric power distribution</subject><subject>Finite difference method</subject><subject>Finite element analysis</subject><subject>Finite element method</subject><subject>Form function</subject><subject>Fuels</subject><subject>Hexagonal core</subject><subject>Mathematical analysis</subject><subject>Neutron flux</subject><subject>Neutrons</subject><subject>Nuclear engineering</subject><subject>Nuclear fuel elements</subject><subject>Nuclear fuels</subject><subject>Nuclear reactors</subject><subject>Nuclear safety</subject><subject>Pin-wise power</subject><subject>Polynomials</subject><subject>Probability</subject><subject>Reconstruction</subject><subject>Studies</subject><subject>TPEN method</subject><issn>0149-1970</issn><issn>1878-4224</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2020</creationdate><recordtype>article</recordtype><recordid>eNqFkM1LAzEQxYMoWKt_ghDwvDWT_cjuSaR-QsGL3oSQJrNtyjZZk6zif--W7d3TwJv33jA_Qq6BLYBBdbtb9G7Q6HDBGT9oOa_5CZlBLeqs4Lw4JTMGRZNBI9g5uYhxxxgIKMsZ-XzAb-x8v0eXqG9p2iJNwSq36TBbq4iGOm9UR1W38cGm7Z62PtCA2ruYwqCTdRvaW0d7_4OBGjuqdj0kO-4vyVmruohXxzknH0-P78uXbPX2_Lq8X2U6z0XKmmpdQYNCgEIDNeeVQQEGhGhLpVpdmhKMqHjZ6tqYteB1bhRyZCVrKtNAPic3U28f_NeAMcmdH4IbT0peFJADKxo-usrJpYOPMWAr-2D3KvxKYPIAUu7kEaQ8gJQTyDF3N-VwfOHbYpBRW3QajR0xJGm8_afhD-3AgFs</recordid><startdate>202004</startdate><enddate>202004</enddate><creator>Safarzadeh, Omid</creator><general>Elsevier Ltd</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope></search><sort><creationdate>202004</creationdate><title>Development of the triangle-based nodal algorithm for reconstructing pin power distributions</title><author>Safarzadeh, Omid</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c337t-96b619e771aed18226de71d177f5aafc5d51d7625fc8ddb7283dae2e05096d913</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2020</creationdate><topic>Algorithms</topic><topic>Electric power distribution</topic><topic>Finite difference method</topic><topic>Finite element analysis</topic><topic>Finite element method</topic><topic>Form function</topic><topic>Fuels</topic><topic>Hexagonal core</topic><topic>Mathematical analysis</topic><topic>Neutron flux</topic><topic>Neutrons</topic><topic>Nuclear engineering</topic><topic>Nuclear fuel elements</topic><topic>Nuclear fuels</topic><topic>Nuclear reactors</topic><topic>Nuclear safety</topic><topic>Pin-wise power</topic><topic>Polynomials</topic><topic>Probability</topic><topic>Reconstruction</topic><topic>Studies</topic><topic>TPEN method</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Safarzadeh, Omid</creatorcontrib><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><jtitle>Progress in nuclear energy (New series)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Safarzadeh, Omid</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Development of the triangle-based nodal algorithm for reconstructing pin power distributions</atitle><jtitle>Progress in nuclear energy (New series)</jtitle><date>2020-04</date><risdate>2020</risdate><volume>122</volume><spage>103282</spage><pages>103282-</pages><artnum>103282</artnum><issn>0149-1970</issn><eissn>1878-4224</eissn><abstract>The fuel pin power is an essential parameter for increasing the safety and reliability features of the reactor. Although the high-order triangle-based polynomial expansion nodal (TPEN) algorithm had been suggested for incredible accuracy and computational speed in hexagonal core analyses, the pin power reconstruction of this algorithm is not developed and assessed. This paper presents the characteristics and performances of the TPEN algorithm for pin power reconstruction. The converged nodal information obtained from sweep between coarse-mesh finite difference (CMFD) and TPEN methods is used to reconstruct the neutron flux distribution in a homogeneous fuel assembly. The modulation technique is used to obtain the heterogeneous distribution of power density. In this technique, the power density homogeneous distribution, calculated with the reconstructed neutron flux is multiplied by a form function. These functions are generated by DRAGON5. The results obtained by this algorithm are verified for various core configurations of a VVER-1000 reactor. The pin power factors show good agreement with the reference solution obtained by heterogeneous fine mesh finite element method. The largest and average relative errors found were of the order of 5% and 0.5% for TPEN, in a peripheral cell of a fuel element with the faces towards the region of the baffle/reflector. We also compared the results with those obtained from the nodal expansion method (NEM). The maximum and mean relative error of 10% and 1% are found by the NEM method.
•The TPEN method is used to obtain pin power distribution.•The results of the TPEN and NEM methods is assessed for pin power reconstruction.•The fine mesh finite difference method is used to obtain the reference value.</abstract><cop>Oxford</cop><pub>Elsevier Ltd</pub><doi>10.1016/j.pnucene.2020.103282</doi></addata></record> |
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subjects | Algorithms Electric power distribution Finite difference method Finite element analysis Finite element method Form function Fuels Hexagonal core Mathematical analysis Neutron flux Neutrons Nuclear engineering Nuclear fuel elements Nuclear fuels Nuclear reactors Nuclear safety Pin-wise power Polynomials Probability Reconstruction Studies TPEN method |
title | Development of the triangle-based nodal algorithm for reconstructing pin power distributions |
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