DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA
•Validation status of DRACCAR, a multi-physics code dedicated to LOCA in LWR.•Computational analysis of multi-rod ballooning, contact and fuel relocation.•Details on the associated thermo-mechanics and thermalhydraulics validation.•Assessment of the modeling capabilities to simulate reflooding and c...
Gespeichert in:
Veröffentlicht in: | Nuclear engineering and design 2018-12, Vol.339, p.202-214 |
---|---|
Hauptverfasser: | , , , , , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
container_end_page | 214 |
---|---|
container_issue | |
container_start_page | 202 |
container_title | Nuclear engineering and design |
container_volume | 339 |
creator | Glantz, T. Taurines, T. Belon, S. De Luze, O. Guillard, G. Jacq, F. |
description | •Validation status of DRACCAR, a multi-physics code dedicated to LOCA in LWR.•Computational analysis of multi-rod ballooning, contact and fuel relocation.•Details on the associated thermo-mechanics and thermalhydraulics validation.•Assessment of the modeling capabilities to simulate reflooding and channel blockage.
Computational predictions concerning ballooning of multiple fuel pin bundles during a loss-of-coolant accident with a final reflooding phase are now more than ever of interest in the framework of light water reactor nuclear safety. To carry out these studies, two difficulties have to be overcome. First, the modeling has to take into account many coupled phenomena such as heat transfer (heat generation, radiation, convection and conduction), hydraulics (multidimensional 2-phase flow, blockage), mechanics (thermal expansion, creep, embrittlement) and chemistry (oxidation, hydriding). Secondly, there are only a few experimental investigations that can help to validate such complex coupled modeling. Over several years, IRSN has developed the 3D computational tool DRACCAR to investigate rod bundle strain during LOCA transients including prediction of the reflooding phase. The DRACCAR code is dedicated to study complex configurations such as the deformation and possible contact between neighboring rods and the associated blockage of thermalhydraulic channels in the ballooned zone of the fuel assembly. To accompany the development of DRACCAR, efforts have been devoted to the validation of the coupling between the thermo-mechanics and thermalhydraulic models – including reflooding – through a comparison to integral experiments dedicated to LOCA. The DRACCAR capabilities and validation status are depicted for the version DRACCAR V2.3.1. DRACCAR provides an interesting insight on LOCA by simulating multi-rod and fluid interaction which cannot be investigated with a classical single rod approach. As a conclusion, some prospects regarding the development and validation of the future version DRACCAR V3 are mentioned. In particular significant evolutions are expected regarding the cladding rupture prediction, the contact simulation and the assessment of the coolability of deformed geometries. These evolutions will be based on the knowledge acquired through the R&D project PERFROI, a project dedicated to LOCA, launched by IRSN in association to other partners and supported by the French National Research Agency (ANR). |
doi_str_mv | 10.1016/j.nucengdes.2018.08.031 |
format | Article |
fullrecord | <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_journals_2130271014</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0029549318301791</els_id><sourcerecordid>2130271014</sourcerecordid><originalsourceid>FETCH-LOGICAL-c392t-7ac7c8e785a360d1e89ae1770b39607a05702c555bcb4e77f2ab81a5577a49aa3</originalsourceid><addsrcrecordid>eNqFkdtq3DAQhkVpodukz1BBb2tHslcrO3fGPQUWNoQUeifG8jjVorVcSU7Yl8uzRd4Nva0YJF1888_hJ-QTZzlnfHO1z8dZ4_jQY8gLxqucpSj5G7LilSwyKerfb8mKsaLOxLou35MPIezZcupiRZ6_3jVt29xd04YeZhtNNv05BqMD1a5HOjifPodpjhCNG8FSSFcCAnXDa4J3Pe3AWudGMz58Sbyz0Blr4jHRPR1mtNSjdfqkQfvZJ45ud21Do4cxGBxjyOkt-Ejvn9w13T2ifzT4dKqR2rALr2E6qxoMp74WgUvybgAb8OPre0F-ff923_7MtrsfN22zzXRZFzGToKWuUFYCyg3rOVY1IJeSdWW9YRKYkKzQQohOd2uUciigqzgIISWsa4Dygnw-607e_Z0xRLV3s0-rCKrgJStksmKdKHmmtHcheBzU5M0B_FFxphaz1F79M0stZimWouQpszlnYhoije5V0GktGnvjUUfVO_NfjRc6gqS4</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2130271014</pqid></control><display><type>article</type><title>DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA</title><source>Access via ScienceDirect (Elsevier)</source><creator>Glantz, T. ; Taurines, T. ; Belon, S. ; De Luze, O. ; Guillard, G. ; Jacq, F.</creator><creatorcontrib>Glantz, T. ; Taurines, T. ; Belon, S. ; De Luze, O. ; Guillard, G. ; Jacq, F.</creatorcontrib><description>•Validation status of DRACCAR, a multi-physics code dedicated to LOCA in LWR.•Computational analysis of multi-rod ballooning, contact and fuel relocation.•Details on the associated thermo-mechanics and thermalhydraulics validation.•Assessment of the modeling capabilities to simulate reflooding and channel blockage.
Computational predictions concerning ballooning of multiple fuel pin bundles during a loss-of-coolant accident with a final reflooding phase are now more than ever of interest in the framework of light water reactor nuclear safety. To carry out these studies, two difficulties have to be overcome. First, the modeling has to take into account many coupled phenomena such as heat transfer (heat generation, radiation, convection and conduction), hydraulics (multidimensional 2-phase flow, blockage), mechanics (thermal expansion, creep, embrittlement) and chemistry (oxidation, hydriding). Secondly, there are only a few experimental investigations that can help to validate such complex coupled modeling. Over several years, IRSN has developed the 3D computational tool DRACCAR to investigate rod bundle strain during LOCA transients including prediction of the reflooding phase. The DRACCAR code is dedicated to study complex configurations such as the deformation and possible contact between neighboring rods and the associated blockage of thermalhydraulic channels in the ballooned zone of the fuel assembly. To accompany the development of DRACCAR, efforts have been devoted to the validation of the coupling between the thermo-mechanics and thermalhydraulic models – including reflooding – through a comparison to integral experiments dedicated to LOCA. The DRACCAR capabilities and validation status are depicted for the version DRACCAR V2.3.1. DRACCAR provides an interesting insight on LOCA by simulating multi-rod and fluid interaction which cannot be investigated with a classical single rod approach. As a conclusion, some prospects regarding the development and validation of the future version DRACCAR V3 are mentioned. In particular significant evolutions are expected regarding the cladding rupture prediction, the contact simulation and the assessment of the coolability of deformed geometries. These evolutions will be based on the knowledge acquired through the R&D project PERFROI, a project dedicated to LOCA, launched by IRSN in association to other partners and supported by the French National Research Agency (ANR).</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2018.08.031</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Cladding ; Codes ; Computational fluid dynamics ; Computer applications ; Computer simulation ; Conduction ; Conduction heating ; Convection ; Deformation ; DRACCAR ; Fluid flow ; Geometry ; Heat generation ; Heat transfer ; Hydraulics ; Knowledge acquisition ; Light water reactors ; LOCA ; Loss of coolant accidents ; Mathematical models ; Mechanics (physics) ; Modeling ; Nuclear accidents & safety ; Nuclear engineering ; Nuclear fuels ; Nuclear safety ; Organic chemistry ; Oxidation ; Physics ; R&D ; Relocation ; Research & development ; Rods ; Safety regulations ; Software ; Strain analysis ; Thermal expansion ; Validation ; Validation studies</subject><ispartof>Nuclear engineering and design, 2018-12, Vol.339, p.202-214</ispartof><rights>2018 Elsevier B.V.</rights><rights>Copyright Elsevier BV Dec 1, 2018</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c392t-7ac7c8e785a360d1e89ae1770b39607a05702c555bcb4e77f2ab81a5577a49aa3</citedby><cites>FETCH-LOGICAL-c392t-7ac7c8e785a360d1e89ae1770b39607a05702c555bcb4e77f2ab81a5577a49aa3</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.2018.08.031$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,780,784,3550,27924,27925,45995</link.rule.ids></links><search><creatorcontrib>Glantz, T.</creatorcontrib><creatorcontrib>Taurines, T.</creatorcontrib><creatorcontrib>Belon, S.</creatorcontrib><creatorcontrib>De Luze, O.</creatorcontrib><creatorcontrib>Guillard, G.</creatorcontrib><creatorcontrib>Jacq, F.</creatorcontrib><title>DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA</title><title>Nuclear engineering and design</title><description>•Validation status of DRACCAR, a multi-physics code dedicated to LOCA in LWR.•Computational analysis of multi-rod ballooning, contact and fuel relocation.•Details on the associated thermo-mechanics and thermalhydraulics validation.•Assessment of the modeling capabilities to simulate reflooding and channel blockage.
Computational predictions concerning ballooning of multiple fuel pin bundles during a loss-of-coolant accident with a final reflooding phase are now more than ever of interest in the framework of light water reactor nuclear safety. To carry out these studies, two difficulties have to be overcome. First, the modeling has to take into account many coupled phenomena such as heat transfer (heat generation, radiation, convection and conduction), hydraulics (multidimensional 2-phase flow, blockage), mechanics (thermal expansion, creep, embrittlement) and chemistry (oxidation, hydriding). Secondly, there are only a few experimental investigations that can help to validate such complex coupled modeling. Over several years, IRSN has developed the 3D computational tool DRACCAR to investigate rod bundle strain during LOCA transients including prediction of the reflooding phase. The DRACCAR code is dedicated to study complex configurations such as the deformation and possible contact between neighboring rods and the associated blockage of thermalhydraulic channels in the ballooned zone of the fuel assembly. To accompany the development of DRACCAR, efforts have been devoted to the validation of the coupling between the thermo-mechanics and thermalhydraulic models – including reflooding – through a comparison to integral experiments dedicated to LOCA. The DRACCAR capabilities and validation status are depicted for the version DRACCAR V2.3.1. DRACCAR provides an interesting insight on LOCA by simulating multi-rod and fluid interaction which cannot be investigated with a classical single rod approach. As a conclusion, some prospects regarding the development and validation of the future version DRACCAR V3 are mentioned. In particular significant evolutions are expected regarding the cladding rupture prediction, the contact simulation and the assessment of the coolability of deformed geometries. These evolutions will be based on the knowledge acquired through the R&D project PERFROI, a project dedicated to LOCA, launched by IRSN in association to other partners and supported by the French National Research Agency (ANR).</description><subject>Cladding</subject><subject>Codes</subject><subject>Computational fluid dynamics</subject><subject>Computer applications</subject><subject>Computer simulation</subject><subject>Conduction</subject><subject>Conduction heating</subject><subject>Convection</subject><subject>Deformation</subject><subject>DRACCAR</subject><subject>Fluid flow</subject><subject>Geometry</subject><subject>Heat generation</subject><subject>Heat transfer</subject><subject>Hydraulics</subject><subject>Knowledge acquisition</subject><subject>Light water reactors</subject><subject>LOCA</subject><subject>Loss of coolant accidents</subject><subject>Mathematical models</subject><subject>Mechanics (physics)</subject><subject>Modeling</subject><subject>Nuclear accidents & safety</subject><subject>Nuclear engineering</subject><subject>Nuclear fuels</subject><subject>Nuclear safety</subject><subject>Organic chemistry</subject><subject>Oxidation</subject><subject>Physics</subject><subject>R&D</subject><subject>Relocation</subject><subject>Research & development</subject><subject>Rods</subject><subject>Safety regulations</subject><subject>Software</subject><subject>Strain analysis</subject><subject>Thermal expansion</subject><subject>Validation</subject><subject>Validation studies</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNqFkdtq3DAQhkVpodukz1BBb2tHslcrO3fGPQUWNoQUeifG8jjVorVcSU7Yl8uzRd4Nva0YJF1888_hJ-QTZzlnfHO1z8dZ4_jQY8gLxqucpSj5G7LilSwyKerfb8mKsaLOxLou35MPIezZcupiRZ6_3jVt29xd04YeZhtNNv05BqMD1a5HOjifPodpjhCNG8FSSFcCAnXDa4J3Pe3AWudGMz58Sbyz0Blr4jHRPR1mtNSjdfqkQfvZJ45ud21Do4cxGBxjyOkt-Ejvn9w13T2ifzT4dKqR2rALr2E6qxoMp74WgUvybgAb8OPre0F-ff923_7MtrsfN22zzXRZFzGToKWuUFYCyg3rOVY1IJeSdWW9YRKYkKzQQohOd2uUciigqzgIISWsa4Dygnw-607e_Z0xRLV3s0-rCKrgJStksmKdKHmmtHcheBzU5M0B_FFxphaz1F79M0stZimWouQpszlnYhoije5V0GktGnvjUUfVO_NfjRc6gqS4</recordid><startdate>20181201</startdate><enddate>20181201</enddate><creator>Glantz, T.</creator><creator>Taurines, T.</creator><creator>Belon, S.</creator><creator>De Luze, O.</creator><creator>Guillard, G.</creator><creator>Jacq, F.</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>20181201</creationdate><title>DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA</title><author>Glantz, T. ; Taurines, T. ; Belon, S. ; De Luze, O. ; Guillard, G. ; Jacq, F.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c392t-7ac7c8e785a360d1e89ae1770b39607a05702c555bcb4e77f2ab81a5577a49aa3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>Cladding</topic><topic>Codes</topic><topic>Computational fluid dynamics</topic><topic>Computer applications</topic><topic>Computer simulation</topic><topic>Conduction</topic><topic>Conduction heating</topic><topic>Convection</topic><topic>Deformation</topic><topic>DRACCAR</topic><topic>Fluid flow</topic><topic>Geometry</topic><topic>Heat generation</topic><topic>Heat transfer</topic><topic>Hydraulics</topic><topic>Knowledge acquisition</topic><topic>Light water reactors</topic><topic>LOCA</topic><topic>Loss of coolant accidents</topic><topic>Mathematical models</topic><topic>Mechanics (physics)</topic><topic>Modeling</topic><topic>Nuclear accidents & safety</topic><topic>Nuclear engineering</topic><topic>Nuclear fuels</topic><topic>Nuclear safety</topic><topic>Organic chemistry</topic><topic>Oxidation</topic><topic>Physics</topic><topic>R&D</topic><topic>Relocation</topic><topic>Research & development</topic><topic>Rods</topic><topic>Safety regulations</topic><topic>Software</topic><topic>Strain analysis</topic><topic>Thermal expansion</topic><topic>Validation</topic><topic>Validation studies</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Glantz, T.</creatorcontrib><creatorcontrib>Taurines, T.</creatorcontrib><creatorcontrib>Belon, S.</creatorcontrib><creatorcontrib>De Luze, O.</creatorcontrib><creatorcontrib>Guillard, G.</creatorcontrib><creatorcontrib>Jacq, F.</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>Glantz, T.</au><au>Taurines, T.</au><au>Belon, S.</au><au>De Luze, O.</au><au>Guillard, G.</au><au>Jacq, F.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA</atitle><jtitle>Nuclear engineering and design</jtitle><date>2018-12-01</date><risdate>2018</risdate><volume>339</volume><spage>202</spage><epage>214</epage><pages>202-214</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><abstract>•Validation status of DRACCAR, a multi-physics code dedicated to LOCA in LWR.•Computational analysis of multi-rod ballooning, contact and fuel relocation.•Details on the associated thermo-mechanics and thermalhydraulics validation.•Assessment of the modeling capabilities to simulate reflooding and channel blockage.
Computational predictions concerning ballooning of multiple fuel pin bundles during a loss-of-coolant accident with a final reflooding phase are now more than ever of interest in the framework of light water reactor nuclear safety. To carry out these studies, two difficulties have to be overcome. First, the modeling has to take into account many coupled phenomena such as heat transfer (heat generation, radiation, convection and conduction), hydraulics (multidimensional 2-phase flow, blockage), mechanics (thermal expansion, creep, embrittlement) and chemistry (oxidation, hydriding). Secondly, there are only a few experimental investigations that can help to validate such complex coupled modeling. Over several years, IRSN has developed the 3D computational tool DRACCAR to investigate rod bundle strain during LOCA transients including prediction of the reflooding phase. The DRACCAR code is dedicated to study complex configurations such as the deformation and possible contact between neighboring rods and the associated blockage of thermalhydraulic channels in the ballooned zone of the fuel assembly. To accompany the development of DRACCAR, efforts have been devoted to the validation of the coupling between the thermo-mechanics and thermalhydraulic models – including reflooding – through a comparison to integral experiments dedicated to LOCA. The DRACCAR capabilities and validation status are depicted for the version DRACCAR V2.3.1. DRACCAR provides an interesting insight on LOCA by simulating multi-rod and fluid interaction which cannot be investigated with a classical single rod approach. As a conclusion, some prospects regarding the development and validation of the future version DRACCAR V3 are mentioned. In particular significant evolutions are expected regarding the cladding rupture prediction, the contact simulation and the assessment of the coolability of deformed geometries. These evolutions will be based on the knowledge acquired through the R&D project PERFROI, a project dedicated to LOCA, launched by IRSN in association to other partners and supported by the French National Research Agency (ANR).</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2018.08.031</doi><tpages>13</tpages><oa>free_for_read</oa></addata></record> |
fulltext | fulltext |
identifier | ISSN: 0029-5493 |
ispartof | Nuclear engineering and design, 2018-12, Vol.339, p.202-214 |
issn | 0029-5493 1872-759X |
language | eng |
recordid | cdi_proquest_journals_2130271014 |
source | Access via ScienceDirect (Elsevier) |
subjects | Cladding Codes Computational fluid dynamics Computer applications Computer simulation Conduction Conduction heating Convection Deformation DRACCAR Fluid flow Geometry Heat generation Heat transfer Hydraulics Knowledge acquisition Light water reactors LOCA Loss of coolant accidents Mathematical models Mechanics (physics) Modeling Nuclear accidents & safety Nuclear engineering Nuclear fuels Nuclear safety Organic chemistry Oxidation Physics R&D Relocation Research & development Rods Safety regulations Software Strain analysis Thermal expansion Validation Validation studies |
title | DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA |
url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-23T03%3A06%3A34IST&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=DRACCAR:%20A%20multi-physics%20code%20for%20computational%20analysis%20of%20multi-rod%20ballooning,%20coolability%20and%20fuel%20relocation%20during%20LOCA%20transients.%20Part%20Two:%20Overview%20of%20modeling%20capabilities%20for%20LOCA&rft.jtitle=Nuclear%20engineering%20and%20design&rft.au=Glantz,%20T.&rft.date=2018-12-01&rft.volume=339&rft.spage=202&rft.epage=214&rft.pages=202-214&rft.issn=0029-5493&rft.eissn=1872-759X&rft_id=info:doi/10.1016/j.nucengdes.2018.08.031&rft_dat=%3Cproquest_cross%3E2130271014%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=2130271014&rft_id=info:pmid/&rft_els_id=S0029549318301791&rfr_iscdi=true |