Verification and validation of the HTGR systems CFD code Flownex
Regulatory requirements prescribe extensive verification and validation (V&V) of computer codes that are used in the design and analysis of accident conditions in nuclear plants. Flownex is a dynamic systems CFD code used as the primary thermal-fluid simulation code by the Pebble Bed Modular Rea...
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Veröffentlicht in: | Nuclear engineering and design 2006-03, Vol.236 (5), p.491-501 |
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creator | van Ravenswaay, Jan P. Greyvenstein, Gideon P. van Niekerk, Willem M.K. Labuschagne, Johan T. |
description | Regulatory requirements prescribe extensive verification and validation (V&V) of computer codes that are used in the design and analysis of accident conditions in nuclear plants. Flownex is a dynamic systems CFD code used as the primary thermal-fluid simulation code by the Pebble Bed Modular Reactor Company (PBMR).
Stringent quality assurance processes have been implemented to ensure that the code conforms to the set standards. These processes include the comparison of Flownex with analytical results as well as with experimental data.
The results of this process are summarized in this paper. Analytical solutions are used to verify Flownex's element models so as to ensure that the basic theory is correctly implemented in the computer code. As part of the analytical V&V effort various well-defined problems are solved using numerical methods implemented in independent computer codes.
Comparison with experimental and plant data is a very important feature of the V&V program to validate that the chosen theory is fit for purpose. For this, validation data from the pebble bed micro model (PBMM) is used. In addition to the PBMM experimental data Flownex is compared to a number of small thermal-fluid experiments in which certain specific component phenomena is validated. These experiments were developed in collaboration with North-West University (previously Potchefstroom University). |
doi_str_mv | 10.1016/j.nucengdes.2005.11.025 |
format | Article |
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Stringent quality assurance processes have been implemented to ensure that the code conforms to the set standards. These processes include the comparison of Flownex with analytical results as well as with experimental data.
The results of this process are summarized in this paper. Analytical solutions are used to verify Flownex's element models so as to ensure that the basic theory is correctly implemented in the computer code. As part of the analytical V&V effort various well-defined problems are solved using numerical methods implemented in independent computer codes.
Comparison with experimental and plant data is a very important feature of the V&V program to validate that the chosen theory is fit for purpose. For this, validation data from the pebble bed micro model (PBMM) is used. In addition to the PBMM experimental data Flownex is compared to a number of small thermal-fluid experiments in which certain specific component phenomena is validated. These experiments were developed in collaboration with North-West University (previously Potchefstroom University).</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2005.11.025</identifier><identifier>CODEN: NEDEAU</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Controled nuclear fusion plants ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fuels ; Installations for energy generation and conversion: thermal and electrical energy ; Nuclear fuels</subject><ispartof>Nuclear engineering and design, 2006-03, Vol.236 (5), p.491-501</ispartof><rights>2006 Elsevier B.V.</rights><rights>2006 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c376t-4663978e0e2f3ac3fe5b9a3f5ad837b5e1a450bc1e9f465faeec568c8394b65b3</citedby><cites>FETCH-LOGICAL-c376t-4663978e0e2f3ac3fe5b9a3f5ad837b5e1a450bc1e9f465faeec568c8394b65b3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0029549306000380$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,776,780,785,786,3537,23909,23910,25118,27901,27902,65534</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=17654322$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>van Ravenswaay, Jan P.</creatorcontrib><creatorcontrib>Greyvenstein, Gideon P.</creatorcontrib><creatorcontrib>van Niekerk, Willem M.K.</creatorcontrib><creatorcontrib>Labuschagne, Johan T.</creatorcontrib><title>Verification and validation of the HTGR systems CFD code Flownex</title><title>Nuclear engineering and design</title><description>Regulatory requirements prescribe extensive verification and validation (V&V) of computer codes that are used in the design and analysis of accident conditions in nuclear plants. Flownex is a dynamic systems CFD code used as the primary thermal-fluid simulation code by the Pebble Bed Modular Reactor Company (PBMR).
Stringent quality assurance processes have been implemented to ensure that the code conforms to the set standards. These processes include the comparison of Flownex with analytical results as well as with experimental data.
The results of this process are summarized in this paper. Analytical solutions are used to verify Flownex's element models so as to ensure that the basic theory is correctly implemented in the computer code. As part of the analytical V&V effort various well-defined problems are solved using numerical methods implemented in independent computer codes.
Comparison with experimental and plant data is a very important feature of the V&V program to validate that the chosen theory is fit for purpose. For this, validation data from the pebble bed micro model (PBMM) is used. In addition to the PBMM experimental data Flownex is compared to a number of small thermal-fluid experiments in which certain specific component phenomena is validated. These experiments were developed in collaboration with North-West University (previously Potchefstroom University).</description><subject>Applied sciences</subject><subject>Controled nuclear fusion plants</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Nuclear fuels</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2006</creationdate><recordtype>article</recordtype><recordid>eNqFkF9LwzAUxYMoOKefwb7oW2v-NEnzpky3CQNBpvgW0vRGM7p2Jt10396ODX30vlwu_M49nIPQJcEZwUTcLLJmbaF5ryBmFGOeEZJhyo_QgBSSppKrt2M0wJiqlOeKnaKzGBd4N4oO0O0rBO-8NZ1vm8Q0VbIxta_2Z-uS7gOS6XzynMRt7GAZk9H4PrFtBcm4br8a-D5HJ87UES4Oe4hexg_z0TSdPU0eR3ez1DIpujQXgilZAAbqmLHMAS-VYY6bqmCy5EBMznFpCSiXC-4MgOWisAVTeSl4yYboev93FdrPNcROL320UNemgXYdNVV9UknyHpR70IY2xgBOr4JfmrDVBOtdY3qhfxvTu8Y0IbpvrFdeHSxMtKZ2wTTWxz-5FDxnlPbc3Z6DPu_GQ9DRemgsVD6A7XTV-n-9fgBUCoWM</recordid><startdate>20060301</startdate><enddate>20060301</enddate><creator>van Ravenswaay, Jan P.</creator><creator>Greyvenstein, Gideon P.</creator><creator>van Niekerk, Willem M.K.</creator><creator>Labuschagne, Johan T.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20060301</creationdate><title>Verification and validation of the HTGR systems CFD code Flownex</title><author>van Ravenswaay, Jan P. ; Greyvenstein, Gideon P. ; van Niekerk, Willem M.K. ; Labuschagne, Johan T.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c376t-4663978e0e2f3ac3fe5b9a3f5ad837b5e1a450bc1e9f465faeec568c8394b65b3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2006</creationdate><topic>Applied sciences</topic><topic>Controled nuclear fusion plants</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Nuclear fuels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>van Ravenswaay, Jan P.</creatorcontrib><creatorcontrib>Greyvenstein, Gideon P.</creatorcontrib><creatorcontrib>van Niekerk, Willem M.K.</creatorcontrib><creatorcontrib>Labuschagne, Johan T.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications 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><jtitle>Nuclear engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>van Ravenswaay, Jan P.</au><au>Greyvenstein, Gideon P.</au><au>van Niekerk, Willem M.K.</au><au>Labuschagne, Johan T.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Verification and validation of the HTGR systems CFD code Flownex</atitle><jtitle>Nuclear engineering and design</jtitle><date>2006-03-01</date><risdate>2006</risdate><volume>236</volume><issue>5</issue><spage>491</spage><epage>501</epage><pages>491-501</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><coden>NEDEAU</coden><abstract>Regulatory requirements prescribe extensive verification and validation (V&V) of computer codes that are used in the design and analysis of accident conditions in nuclear plants. Flownex is a dynamic systems CFD code used as the primary thermal-fluid simulation code by the Pebble Bed Modular Reactor Company (PBMR).
Stringent quality assurance processes have been implemented to ensure that the code conforms to the set standards. These processes include the comparison of Flownex with analytical results as well as with experimental data.
The results of this process are summarized in this paper. Analytical solutions are used to verify Flownex's element models so as to ensure that the basic theory is correctly implemented in the computer code. As part of the analytical V&V effort various well-defined problems are solved using numerical methods implemented in independent computer codes.
Comparison with experimental and plant data is a very important feature of the V&V program to validate that the chosen theory is fit for purpose. For this, validation data from the pebble bed micro model (PBMM) is used. In addition to the PBMM experimental data Flownex is compared to a number of small thermal-fluid experiments in which certain specific component phenomena is validated. These experiments were developed in collaboration with North-West University (previously Potchefstroom University).</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2005.11.025</doi><tpages>11</tpages></addata></record> |
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subjects | Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Installations for energy generation and conversion: thermal and electrical energy Nuclear fuels |
title | Verification and validation of the HTGR systems CFD code Flownex |
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