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...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:Progress in nuclear energy (New series) 2020-04, Vol.122, p.103282, Article 103282
1. Verfasser: Safarzadeh, Omid
Format: Artikel
Sprache:eng
Schlagworte:
Online-Zugang:Volltext
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
container_end_page
container_issue
container_start_page 103282
container_title Progress in nuclear energy (New series)
container_volume 122
creator Safarzadeh, Omid
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
format Article
fullrecord <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_journals_2441310492</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S014919702030041X</els_id><sourcerecordid>2441310492</sourcerecordid><originalsourceid>FETCH-LOGICAL-c337t-96b619e771aed18226de71d177f5aafc5d51d7625fc8ddb7283dae2e05096d913</originalsourceid><addsrcrecordid>eNqFkM1LAzEQxYMoWKt_ghDwvDWT_cjuSaR-QsGL3oSQJrNtyjZZk6zif--W7d3TwJv33jA_Qq6BLYBBdbtb9G7Q6HDBGT9oOa_5CZlBLeqs4Lw4JTMGRZNBI9g5uYhxxxgIKMsZ-XzAb-x8v0eXqG9p2iJNwSq36TBbq4iGOm9UR1W38cGm7Z62PtCA2ruYwqCTdRvaW0d7_4OBGjuqdj0kO-4vyVmruohXxzknH0-P78uXbPX2_Lq8X2U6z0XKmmpdQYNCgEIDNeeVQQEGhGhLpVpdmhKMqHjZ6tqYteB1bhRyZCVrKtNAPic3U28f_NeAMcmdH4IbT0peFJADKxo-usrJpYOPMWAr-2D3KvxKYPIAUu7kEaQ8gJQTyDF3N-VwfOHbYpBRW3QajR0xJGm8_afhD-3AgFs</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2441310492</pqid></control><display><type>article</type><title>Development of the triangle-based nodal algorithm for reconstructing pin power distributions</title><source>Access via ScienceDirect (Elsevier)</source><creator>Safarzadeh, Omid</creator><creatorcontrib>Safarzadeh, Omid</creatorcontrib><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><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 &amp; 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>
fulltext fulltext
identifier ISSN: 0149-1970
ispartof Progress in nuclear energy (New series), 2020-04, Vol.122, p.103282, Article 103282
issn 0149-1970
1878-4224
language eng
recordid cdi_proquest_journals_2441310492
source Access via ScienceDirect (Elsevier)
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
url https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-24T21%3A40%3A55IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_cross&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Development%20of%20the%20triangle-based%20nodal%20algorithm%20for%20reconstructing%20pin%20power%20distributions&rft.jtitle=Progress%20in%20nuclear%20energy%20(New%20series)&rft.au=Safarzadeh,%20Omid&rft.date=2020-04&rft.volume=122&rft.spage=103282&rft.pages=103282-&rft.artnum=103282&rft.issn=0149-1970&rft.eissn=1878-4224&rft_id=info:doi/10.1016/j.pnucene.2020.103282&rft_dat=%3Cproquest_cross%3E2441310492%3C/proquest_cross%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=2441310492&rft_id=info:pmid/&rft_els_id=S014919702030041X&rfr_iscdi=true