Development and validation of the multi-physics DRACCAR code
•Recent advances in the development and validation of the DRACCAR code are presented.•Experimental programs dealing with reflooding of an intact or ballooned bundle are simulated.•Ways of improvement have been identified and are in progress such as a new reflooding model and a 6 equation version of...
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Veröffentlicht in: | Annals of nuclear energy 2015-10, Vol.84, p.1-18 |
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creator | Bascou, S. De Luze, O. Ederli, S. Guillard, G. |
description | •Recent advances in the development and validation of the DRACCAR code are presented.•Experimental programs dealing with reflooding of an intact or ballooned bundle are simulated.•Ways of improvement have been identified and are in progress such as a new reflooding model and a 6 equation version of the thermal–hydraulics code.•Spent-fuel-pool draining accidents are addressed and the modeling flexibility of the DRACCAR code to model non axis-symmetric systems is emphasized.
To meet the simulation needs of its LOCA R&D program, the IRSN is developing a multi-rod computational tool named DRACCAR. In order to realistically describe the behavior of the reactor core during a Loss Of Coolant Accident (LOCA), modeling has to take into account many coupled phenomena such as thermics (heat generation, radiation, convection and conduction), hydraulics (multi dimensional 1–3 phase flow, shrinkage), mechanics (thermal dilatation, creep, embrittlement) and chemistry (oxidation, oxygen diffusion, hydriding,...). This paper presents several aspects of the DRACCAR code abilities: first to handle thermal–hydraulics during reflooding of an intact and of a partially ballooned bundle and secondly the simulation of the OECD SFP phase II experiment dealing with the instantaneous draining of a spent fuel pool. |
doi_str_mv | 10.1016/j.anucene.2014.09.040 |
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To meet the simulation needs of its LOCA R&D program, the IRSN is developing a multi-rod computational tool named DRACCAR. In order to realistically describe the behavior of the reactor core during a Loss Of Coolant Accident (LOCA), modeling has to take into account many coupled phenomena such as thermics (heat generation, radiation, convection and conduction), hydraulics (multi dimensional 1–3 phase flow, shrinkage), mechanics (thermal dilatation, creep, embrittlement) and chemistry (oxidation, oxygen diffusion, hydriding,...). This paper presents several aspects of the DRACCAR code abilities: first to handle thermal–hydraulics during reflooding of an intact and of a partially ballooned bundle and secondly the simulation of the OECD SFP phase II experiment dealing with the instantaneous draining of a spent fuel pool.</description><identifier>ISSN: 0306-4549</identifier><identifier>EISSN: 1873-2100</identifier><identifier>DOI: 10.1016/j.anucene.2014.09.040</identifier><language>eng</language><publisher>Elsevier Ltd</publisher><subject>Achilles ; Bundling ; Computer simulation ; Conduction heating ; DRACCAR ; Embrittlement ; LOCA ; Mathematical models ; Nuclear reactor components ; Physics ; Reflooding ; Spent fuel pool ; THETIS</subject><ispartof>Annals of nuclear energy, 2015-10, Vol.84, p.1-18</ispartof><rights>2014 Elsevier Ltd</rights><rights>Distributed under a Creative Commons Attribution 4.0 International License</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c462t-94a701bee66291352b0daab41802363d7d4f40e6274a0f4b19888fed2570d4083</citedby><cites>FETCH-LOGICAL-c462t-94a701bee66291352b0daab41802363d7d4f40e6274a0f4b19888fed2570d4083</cites><orcidid>0000-0003-0654-7253</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.anucene.2014.09.040$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>230,314,780,784,885,3541,27915,27916,45986</link.rule.ids><backlink>$$Uhttps://hal.science/hal-02572583$$DView record in HAL$$Hfree_for_read</backlink></links><search><creatorcontrib>Bascou, S.</creatorcontrib><creatorcontrib>De Luze, O.</creatorcontrib><creatorcontrib>Ederli, S.</creatorcontrib><creatorcontrib>Guillard, G.</creatorcontrib><title>Development and validation of the multi-physics DRACCAR code</title><title>Annals of nuclear energy</title><description>•Recent advances in the development and validation of the DRACCAR code are presented.•Experimental programs dealing with reflooding of an intact or ballooned bundle are simulated.•Ways of improvement have been identified and are in progress such as a new reflooding model and a 6 equation version of the thermal–hydraulics code.•Spent-fuel-pool draining accidents are addressed and the modeling flexibility of the DRACCAR code to model non axis-symmetric systems is emphasized.
To meet the simulation needs of its LOCA R&D program, the IRSN is developing a multi-rod computational tool named DRACCAR. In order to realistically describe the behavior of the reactor core during a Loss Of Coolant Accident (LOCA), modeling has to take into account many coupled phenomena such as thermics (heat generation, radiation, convection and conduction), hydraulics (multi dimensional 1–3 phase flow, shrinkage), mechanics (thermal dilatation, creep, embrittlement) and chemistry (oxidation, oxygen diffusion, hydriding,...). This paper presents several aspects of the DRACCAR code abilities: first to handle thermal–hydraulics during reflooding of an intact and of a partially ballooned bundle and secondly the simulation of the OECD SFP phase II experiment dealing with the instantaneous draining of a spent fuel pool.</description><subject>Achilles</subject><subject>Bundling</subject><subject>Computer simulation</subject><subject>Conduction heating</subject><subject>DRACCAR</subject><subject>Embrittlement</subject><subject>LOCA</subject><subject>Mathematical models</subject><subject>Nuclear reactor components</subject><subject>Physics</subject><subject>Reflooding</subject><subject>Spent fuel pool</subject><subject>THETIS</subject><issn>0306-4549</issn><issn>1873-2100</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2015</creationdate><recordtype>article</recordtype><recordid>eNqNkU1LxDAQhoMouK7-BKFHPbRO0vQLBCm76goLwqLnkCZTNkvb1KYt7L-3S8WrngaG550Z5iHklkJAgcYPh0A2g8IGAwaUB5AFwOGMLGiahD6jAOdkASHEPo94dkmunDsAUJZyviCPaxyxsm2NTe_JRnujrIyWvbGNZ0uv36NXD1Vv_HZ_dEY5b73LV6t85ymr8ZpclLJyePNTl-Tz5fljtfG3769vq3zrKx6z3s-4TIAWiHHMMhpGrAAtZcFpCiyMQ51oXnLAmCVcQskLmqVpWqJmUQKaQxouyf08dy8r0Xamlt1RWGnEJt-KUw8mlEVpONKJvZvZtrNfA7pe1MYprCrZoB2coAlkSTit4P9BI8jYxE5oNKOqs851WP6eQUGcJIiD-JEgThIEZGKSMOWe5hxO7xkNdsIpg41CbTpUvdDW_DHhG2crjws</recordid><startdate>20151001</startdate><enddate>20151001</enddate><creator>Bascou, S.</creator><creator>De Luze, O.</creator><creator>Ederli, S.</creator><creator>Guillard, G.</creator><general>Elsevier Ltd</general><general>Elsevier Masson</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7ST</scope><scope>7T2</scope><scope>7U2</scope><scope>C1K</scope><scope>SOI</scope><scope>7SP</scope><scope>7SU</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope><scope>1XC</scope><orcidid>https://orcid.org/0000-0003-0654-7253</orcidid></search><sort><creationdate>20151001</creationdate><title>Development and validation of the multi-physics DRACCAR code</title><author>Bascou, S. ; De Luze, O. ; Ederli, S. ; Guillard, G.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c462t-94a701bee66291352b0daab41802363d7d4f40e6274a0f4b19888fed2570d4083</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2015</creationdate><topic>Achilles</topic><topic>Bundling</topic><topic>Computer simulation</topic><topic>Conduction heating</topic><topic>DRACCAR</topic><topic>Embrittlement</topic><topic>LOCA</topic><topic>Mathematical models</topic><topic>Nuclear reactor components</topic><topic>Physics</topic><topic>Reflooding</topic><topic>Spent fuel pool</topic><topic>THETIS</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Bascou, S.</creatorcontrib><creatorcontrib>De Luze, O.</creatorcontrib><creatorcontrib>Ederli, S.</creatorcontrib><creatorcontrib>Guillard, G.</creatorcontrib><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Health and Safety Science Abstracts (Full archive)</collection><collection>Safety Science and Risk</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><collection>Electronics & Communications Abstracts</collection><collection>Environmental Engineering Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Hyper Article en Ligne (HAL)</collection><jtitle>Annals of nuclear energy</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Bascou, S.</au><au>De Luze, O.</au><au>Ederli, S.</au><au>Guillard, G.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Development and validation of the multi-physics DRACCAR code</atitle><jtitle>Annals of nuclear energy</jtitle><date>2015-10-01</date><risdate>2015</risdate><volume>84</volume><spage>1</spage><epage>18</epage><pages>1-18</pages><issn>0306-4549</issn><eissn>1873-2100</eissn><abstract>•Recent advances in the development and validation of the DRACCAR code are presented.•Experimental programs dealing with reflooding of an intact or ballooned bundle are simulated.•Ways of improvement have been identified and are in progress such as a new reflooding model and a 6 equation version of the thermal–hydraulics code.•Spent-fuel-pool draining accidents are addressed and the modeling flexibility of the DRACCAR code to model non axis-symmetric systems is emphasized.
To meet the simulation needs of its LOCA R&D program, the IRSN is developing a multi-rod computational tool named DRACCAR. In order to realistically describe the behavior of the reactor core during a Loss Of Coolant Accident (LOCA), modeling has to take into account many coupled phenomena such as thermics (heat generation, radiation, convection and conduction), hydraulics (multi dimensional 1–3 phase flow, shrinkage), mechanics (thermal dilatation, creep, embrittlement) and chemistry (oxidation, oxygen diffusion, hydriding,...). This paper presents several aspects of the DRACCAR code abilities: first to handle thermal–hydraulics during reflooding of an intact and of a partially ballooned bundle and secondly the simulation of the OECD SFP phase II experiment dealing with the instantaneous draining of a spent fuel pool.</abstract><pub>Elsevier Ltd</pub><doi>10.1016/j.anucene.2014.09.040</doi><tpages>18</tpages><orcidid>https://orcid.org/0000-0003-0654-7253</orcidid></addata></record> |
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source | ScienceDirect Journals (5 years ago - present) |
subjects | Achilles Bundling Computer simulation Conduction heating DRACCAR Embrittlement LOCA Mathematical models Nuclear reactor components Physics Reflooding Spent fuel pool THETIS |
title | Development and validation of the multi-physics DRACCAR code |
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