A Review of Finite Element Method Models for Nuclear Graphite Applications

Graphite components serve as structural support and as a neutron moderator in multiple nuclear power stations and is also a prospective material in Generation IV reactor concepts. The environment (e.g. high temperature and intense radiation) within a graphite core changes the geometry, microstructur...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:Archives of computational methods in engineering 2020-01, Vol.27 (1), p.331-350
Hauptverfasser: Arregui-Mena, José David, Worth, Robert N., Hall, Graham, Edmondson, Philip D., Giorla, Alain B., Burchell, Timothy D.
Format: Artikel
Sprache:eng
Schlagworte:
Online-Zugang:Volltext
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
container_end_page 350
container_issue 1
container_start_page 331
container_title Archives of computational methods in engineering
container_volume 27
creator Arregui-Mena, José David
Worth, Robert N.
Hall, Graham
Edmondson, Philip D.
Giorla, Alain B.
Burchell, Timothy D.
description Graphite components serve as structural support and as a neutron moderator in multiple nuclear power stations and is also a prospective material in Generation IV reactor concepts. The environment (e.g. high temperature and intense radiation) within a graphite core changes the geometry, microstructure and material properties of the graphite components, that could limit the lifetime (i.e. safe operation) of a reactor. Some of the assessments made for graphite reactor core components include Finite Element Method (FEM) simulations. These simulations are used to estimate the stress state and strain state and probability of failure of irradiated graphite components. FEM also forms part of the validation of measurements or as a complementary technique to experimental procedures in graphite research. A comprehensive overview of FEM methodologies is provided in this review, including: FEM software, basics steps to set up a FEM model, and analytical solutions used to validate simulations for this field of study. The objective of this paper is to inform researchers in the different available FEM techniques and tools used in the research of nuclear graphite.
doi_str_mv 10.1007/s11831-018-09310-y
format Article
fullrecord <record><control><sourceid>proquest_osti_</sourceid><recordid>TN_cdi_osti_scitechconnect_1509562</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>2332097106</sourcerecordid><originalsourceid>FETCH-LOGICAL-c418t-67e1f24e9a5ecbfc7855a9caa94b3ca0a6ad950d1037430395d6bbafc13e1d3</originalsourceid><addsrcrecordid>eNp9kMFOwzAQRCMEElD4AU4WnAO7cRzHx6qCAmpBAu6W42xoqhAHOwX170kJEreedg9vRqMXRRcI1wggbwJizjEGzGNQHCHeHkQnmOdZjDJPD4cfeRpzyOA4Og1hDSBSpZKT6HHKXuirpm_mKnZXt3VP7LahD2p7tqR-5Uq2dCU1gVXOs6eNbch4NvemW-3Qadc1tTV97dpwFh1Vpgl0_ncn0evd7dvsPl48zx9m00VsU8z7OJOEVZKSMoJsUVmZC2GUNUalBbcGTGZKJaBE4DLlwJUos6IwlUVOWPJJdDm2utDXOthhhV1Z17Zke40ClMiSAboaoc67zw2FXq_dxrfDKp1wnoCSCNleCoWUAImEgUpGynoXgqdKd77-MH6rEfROvh7l60G-_pWvt0OIj6EwwO07-f_qPakfalaGIQ</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2157700270</pqid></control><display><type>article</type><title>A Review of Finite Element Method Models for Nuclear Graphite Applications</title><source>SpringerLink Journals - AutoHoldings</source><creator>Arregui-Mena, José David ; Worth, Robert N. ; Hall, Graham ; Edmondson, Philip D. ; Giorla, Alain B. ; Burchell, Timothy D.</creator><creatorcontrib>Arregui-Mena, José David ; Worth, Robert N. ; Hall, Graham ; Edmondson, Philip D. ; Giorla, Alain B. ; Burchell, Timothy D. ; Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><description>Graphite components serve as structural support and as a neutron moderator in multiple nuclear power stations and is also a prospective material in Generation IV reactor concepts. The environment (e.g. high temperature and intense radiation) within a graphite core changes the geometry, microstructure and material properties of the graphite components, that could limit the lifetime (i.e. safe operation) of a reactor. Some of the assessments made for graphite reactor core components include Finite Element Method (FEM) simulations. These simulations are used to estimate the stress state and strain state and probability of failure of irradiated graphite components. FEM also forms part of the validation of measurements or as a complementary technique to experimental procedures in graphite research. A comprehensive overview of FEM methodologies is provided in this review, including: FEM software, basics steps to set up a FEM model, and analytical solutions used to validate simulations for this field of study. The objective of this paper is to inform researchers in the different available FEM techniques and tools used in the research of nuclear graphite.</description><identifier>ISSN: 1134-3060</identifier><identifier>EISSN: 1886-1784</identifier><identifier>DOI: 10.1007/s11831-018-09310-y</identifier><language>eng</language><publisher>Dordrecht: Springer Netherlands</publisher><subject>Computer simulation ; ENGINEERING ; Exact solutions ; Finite element analysis ; Finite element method ; Graphite ; High temperature ; Material properties ; Mathematical and Computational Engineering ; Mathematical models ; Nuclear power plants ; Nuclear reactors ; Original Paper ; Power plants ; Simulation</subject><ispartof>Archives of computational methods in engineering, 2020-01, Vol.27 (1), p.331-350</ispartof><rights>CIMNE, Barcelona, Spain 2018</rights><rights>Archives of Computational Methods in Engineering is a copyright of Springer, (2018). All Rights Reserved.</rights><rights>Copyright Springer Nature B.V. 2020</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c418t-67e1f24e9a5ecbfc7855a9caa94b3ca0a6ad950d1037430395d6bbafc13e1d3</citedby><cites>FETCH-LOGICAL-c418t-67e1f24e9a5ecbfc7855a9caa94b3ca0a6ad950d1037430395d6bbafc13e1d3</cites><orcidid>0000-0002-6131-3268 ; 0000000277500789 ; 0000000261313268 ; 0000000189900870 ; 0000000314361192</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1007/s11831-018-09310-y$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1007/s11831-018-09310-y$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>230,314,780,784,885,27924,27925,41488,42557,51319</link.rule.ids><backlink>$$Uhttps://www.osti.gov/servlets/purl/1509562$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Arregui-Mena, José David</creatorcontrib><creatorcontrib>Worth, Robert N.</creatorcontrib><creatorcontrib>Hall, Graham</creatorcontrib><creatorcontrib>Edmondson, Philip D.</creatorcontrib><creatorcontrib>Giorla, Alain B.</creatorcontrib><creatorcontrib>Burchell, Timothy D.</creatorcontrib><creatorcontrib>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><title>A Review of Finite Element Method Models for Nuclear Graphite Applications</title><title>Archives of computational methods in engineering</title><addtitle>Arch Computat Methods Eng</addtitle><description>Graphite components serve as structural support and as a neutron moderator in multiple nuclear power stations and is also a prospective material in Generation IV reactor concepts. The environment (e.g. high temperature and intense radiation) within a graphite core changes the geometry, microstructure and material properties of the graphite components, that could limit the lifetime (i.e. safe operation) of a reactor. Some of the assessments made for graphite reactor core components include Finite Element Method (FEM) simulations. These simulations are used to estimate the stress state and strain state and probability of failure of irradiated graphite components. FEM also forms part of the validation of measurements or as a complementary technique to experimental procedures in graphite research. A comprehensive overview of FEM methodologies is provided in this review, including: FEM software, basics steps to set up a FEM model, and analytical solutions used to validate simulations for this field of study. The objective of this paper is to inform researchers in the different available FEM techniques and tools used in the research of nuclear graphite.</description><subject>Computer simulation</subject><subject>ENGINEERING</subject><subject>Exact solutions</subject><subject>Finite element analysis</subject><subject>Finite element method</subject><subject>Graphite</subject><subject>High temperature</subject><subject>Material properties</subject><subject>Mathematical and Computational Engineering</subject><subject>Mathematical models</subject><subject>Nuclear power plants</subject><subject>Nuclear reactors</subject><subject>Original Paper</subject><subject>Power plants</subject><subject>Simulation</subject><issn>1134-3060</issn><issn>1886-1784</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2020</creationdate><recordtype>article</recordtype><sourceid>ABUWG</sourceid><sourceid>AFKRA</sourceid><sourceid>AZQEC</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><sourceid>GNUQQ</sourceid><recordid>eNp9kMFOwzAQRCMEElD4AU4WnAO7cRzHx6qCAmpBAu6W42xoqhAHOwX170kJEreedg9vRqMXRRcI1wggbwJizjEGzGNQHCHeHkQnmOdZjDJPD4cfeRpzyOA4Og1hDSBSpZKT6HHKXuirpm_mKnZXt3VP7LahD2p7tqR-5Uq2dCU1gVXOs6eNbch4NvemW-3Qadc1tTV97dpwFh1Vpgl0_ncn0evd7dvsPl48zx9m00VsU8z7OJOEVZKSMoJsUVmZC2GUNUalBbcGTGZKJaBE4DLlwJUos6IwlUVOWPJJdDm2utDXOthhhV1Z17Zke40ClMiSAboaoc67zw2FXq_dxrfDKp1wnoCSCNleCoWUAImEgUpGynoXgqdKd77-MH6rEfROvh7l60G-_pWvt0OIj6EwwO07-f_qPakfalaGIQ</recordid><startdate>20200101</startdate><enddate>20200101</enddate><creator>Arregui-Mena, José David</creator><creator>Worth, Robert N.</creator><creator>Hall, Graham</creator><creator>Edmondson, Philip D.</creator><creator>Giorla, Alain B.</creator><creator>Burchell, Timothy D.</creator><general>Springer Netherlands</general><general>Springer Nature B.V</general><general>Springer Nature</general><scope>AAYXX</scope><scope>CITATION</scope><scope>3V.</scope><scope>7WY</scope><scope>7WZ</scope><scope>7XB</scope><scope>87Z</scope><scope>8AL</scope><scope>8FE</scope><scope>8FG</scope><scope>8FK</scope><scope>8FL</scope><scope>ABJCF</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>ARAPS</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>BEZIV</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>DWQXO</scope><scope>FRNLG</scope><scope>F~G</scope><scope>GNUQQ</scope><scope>HCIFZ</scope><scope>JQ2</scope><scope>K60</scope><scope>K6~</scope><scope>K7-</scope><scope>L.-</scope><scope>L6V</scope><scope>M0C</scope><scope>M0N</scope><scope>M7S</scope><scope>P5Z</scope><scope>P62</scope><scope>PQBIZ</scope><scope>PQBZA</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>PTHSS</scope><scope>PYYUZ</scope><scope>Q9U</scope><scope>OIOZB</scope><scope>OTOTI</scope><orcidid>https://orcid.org/0000-0002-6131-3268</orcidid><orcidid>https://orcid.org/0000000277500789</orcidid><orcidid>https://orcid.org/0000000261313268</orcidid><orcidid>https://orcid.org/0000000189900870</orcidid><orcidid>https://orcid.org/0000000314361192</orcidid></search><sort><creationdate>20200101</creationdate><title>A Review of Finite Element Method Models for Nuclear Graphite Applications</title><author>Arregui-Mena, José David ; Worth, Robert N. ; Hall, Graham ; Edmondson, Philip D. ; Giorla, Alain B. ; Burchell, Timothy D.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c418t-67e1f24e9a5ecbfc7855a9caa94b3ca0a6ad950d1037430395d6bbafc13e1d3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2020</creationdate><topic>Computer simulation</topic><topic>ENGINEERING</topic><topic>Exact solutions</topic><topic>Finite element analysis</topic><topic>Finite element method</topic><topic>Graphite</topic><topic>High temperature</topic><topic>Material properties</topic><topic>Mathematical and Computational Engineering</topic><topic>Mathematical models</topic><topic>Nuclear power plants</topic><topic>Nuclear reactors</topic><topic>Original Paper</topic><topic>Power plants</topic><topic>Simulation</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Arregui-Mena, José David</creatorcontrib><creatorcontrib>Worth, Robert N.</creatorcontrib><creatorcontrib>Hall, Graham</creatorcontrib><creatorcontrib>Edmondson, Philip D.</creatorcontrib><creatorcontrib>Giorla, Alain B.</creatorcontrib><creatorcontrib>Burchell, Timothy D.</creatorcontrib><creatorcontrib>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><collection>CrossRef</collection><collection>ProQuest Central (Corporate)</collection><collection>ABI/INFORM Collection</collection><collection>ABI/INFORM Global (PDF only)</collection><collection>ProQuest Central (purchase pre-March 2016)</collection><collection>ABI/INFORM Global (Alumni Edition)</collection><collection>Computing Database (Alumni Edition)</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>ProQuest Central (Alumni) (purchase pre-March 2016)</collection><collection>ABI/INFORM Collection (Alumni Edition)</collection><collection>Materials Science &amp; Engineering Collection</collection><collection>ProQuest Central (Alumni Edition)</collection><collection>ProQuest Central UK/Ireland</collection><collection>Advanced Technologies &amp; Aerospace Collection</collection><collection>ProQuest Central Essentials</collection><collection>ProQuest Central</collection><collection>Business Premium Collection</collection><collection>Technology Collection</collection><collection>ProQuest One Community College</collection><collection>ProQuest Central Korea</collection><collection>Business Premium Collection (Alumni)</collection><collection>ABI/INFORM Global (Corporate)</collection><collection>ProQuest Central Student</collection><collection>SciTech Premium Collection</collection><collection>ProQuest Computer Science Collection</collection><collection>ProQuest Business Collection (Alumni Edition)</collection><collection>ProQuest Business Collection</collection><collection>Computer Science Database</collection><collection>ABI/INFORM Professional Advanced</collection><collection>ProQuest Engineering Collection</collection><collection>ABI/INFORM Global</collection><collection>Computing Database</collection><collection>Engineering Database</collection><collection>Advanced Technologies &amp; Aerospace Database</collection><collection>ProQuest Advanced Technologies &amp; Aerospace Collection</collection><collection>ProQuest One Business</collection><collection>ProQuest One Business (Alumni)</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><collection>Engineering Collection</collection><collection>ABI/INFORM Collection China</collection><collection>ProQuest Central Basic</collection><collection>OSTI.GOV - Hybrid</collection><collection>OSTI.GOV</collection><jtitle>Archives of computational methods in engineering</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Arregui-Mena, José David</au><au>Worth, Robert N.</au><au>Hall, Graham</au><au>Edmondson, Philip D.</au><au>Giorla, Alain B.</au><au>Burchell, Timothy D.</au><aucorp>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>A Review of Finite Element Method Models for Nuclear Graphite Applications</atitle><jtitle>Archives of computational methods in engineering</jtitle><stitle>Arch Computat Methods Eng</stitle><date>2020-01-01</date><risdate>2020</risdate><volume>27</volume><issue>1</issue><spage>331</spage><epage>350</epage><pages>331-350</pages><issn>1134-3060</issn><eissn>1886-1784</eissn><abstract>Graphite components serve as structural support and as a neutron moderator in multiple nuclear power stations and is also a prospective material in Generation IV reactor concepts. The environment (e.g. high temperature and intense radiation) within a graphite core changes the geometry, microstructure and material properties of the graphite components, that could limit the lifetime (i.e. safe operation) of a reactor. Some of the assessments made for graphite reactor core components include Finite Element Method (FEM) simulations. These simulations are used to estimate the stress state and strain state and probability of failure of irradiated graphite components. FEM also forms part of the validation of measurements or as a complementary technique to experimental procedures in graphite research. A comprehensive overview of FEM methodologies is provided in this review, including: FEM software, basics steps to set up a FEM model, and analytical solutions used to validate simulations for this field of study. The objective of this paper is to inform researchers in the different available FEM techniques and tools used in the research of nuclear graphite.</abstract><cop>Dordrecht</cop><pub>Springer Netherlands</pub><doi>10.1007/s11831-018-09310-y</doi><tpages>20</tpages><orcidid>https://orcid.org/0000-0002-6131-3268</orcidid><orcidid>https://orcid.org/0000000277500789</orcidid><orcidid>https://orcid.org/0000000261313268</orcidid><orcidid>https://orcid.org/0000000189900870</orcidid><orcidid>https://orcid.org/0000000314361192</orcidid><oa>free_for_read</oa></addata></record>
fulltext fulltext
identifier ISSN: 1134-3060
ispartof Archives of computational methods in engineering, 2020-01, Vol.27 (1), p.331-350
issn 1134-3060
1886-1784
language eng
recordid cdi_osti_scitechconnect_1509562
source SpringerLink Journals - AutoHoldings
subjects Computer simulation
ENGINEERING
Exact solutions
Finite element analysis
Finite element method
Graphite
High temperature
Material properties
Mathematical and Computational Engineering
Mathematical models
Nuclear power plants
Nuclear reactors
Original Paper
Power plants
Simulation
title A Review of Finite Element Method Models for Nuclear Graphite Applications
url https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-06T07%3A42%3A29IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_osti_&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=A%20Review%20of%20Finite%20Element%20Method%20Models%20for%20Nuclear%20Graphite%20Applications&rft.jtitle=Archives%20of%20computational%20methods%20in%20engineering&rft.au=Arregui-Mena,%20Jos%C3%A9%20David&rft.aucorp=Oak%20Ridge%20National%20Laboratory%20(ORNL),%20Oak%20Ridge,%20TN%20(United%20States)&rft.date=2020-01-01&rft.volume=27&rft.issue=1&rft.spage=331&rft.epage=350&rft.pages=331-350&rft.issn=1134-3060&rft.eissn=1886-1784&rft_id=info:doi/10.1007/s11831-018-09310-y&rft_dat=%3Cproquest_osti_%3E2332097106%3C/proquest_osti_%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=2157700270&rft_id=info:pmid/&rfr_iscdi=true