Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3
•A file-based, one-way coupling with BISON fuel performance simulations is presented.•This capability can be used as a screen tool for pellet clad interaction.•Allows for insight into the fuel performance physics through VERA simulations.•Cycles 1–3 of Watts Bar Nuclear Unit 1 are highlighted. The C...
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creator | Stimpson, Shane Powers, Jeffrey Clarno, Kevin Pawlowski, Roger Gardner, Russell Novascone, Stephen Gamble, Kyle Williamson, Richard |
description | •A file-based, one-way coupling with BISON fuel performance simulations is presented.•This capability can be used as a screen tool for pellet clad interaction.•Allows for insight into the fuel performance physics through VERA simulations.•Cycles 1–3 of Watts Bar Nuclear Unit 1 are highlighted.
The Consortium for Advanced Simulation of Light Water Reactors (CASL) aims to provide high-fidelity multiphysics simulations of light water nuclear reactors. To accomplish this, CASL is developing the Virtual Environment for Reactor Applications (VERA), which is a suite of code packages for thermal hydraulics, neutron transport, fuel performance, and coolant chemistry. As VERA continues to grow and expand, there has been an increased focus on incorporating fuel performance analysis methods. One of the primary goals of CASL is to estimate local cladding failure probability through pellet-clad interaction, which consists of both pellet-clad mechanical interaction (PCMI) and stress corrosion cracking. Estimating clad failure is important to preventing release of fission products to the primary system and accurate estimates could prove useful in establishing less conservative power ramp rates or when considering load-follow operations.
While this capability is being pursued through several different approaches, the procedure presented in this article focuses on running independent fuel performance calculations with BISON using a file-based one-way coupling based on multicycle output data from high fidelity, pin-resolved coupled neutron transport–thermal hydraulics simulations. This type of approach is consistent with traditional fuel performance analysis methods, which are typically separate from core simulation analyses. A more tightly coupled approach is currently being developed, which is the ultimate target application in CASL.
Recent work simulating 12 cycles of Watts Bar Unit 1 with VERA core simulator are capitalized upon, and quarter-core BISON results for parameters of interest to PCMI (maximum centerline fuel temperature, maximum clad hoop stress, and minimum gap size) are presented for Cycles 1–3. Based on these results, this capability demonstrates its value and how it could be used as a screening tool for gathering insight into PCMI, singling out limiting rods for further, more detailed analysis. |
doi_str_mv | 10.1016/j.nucengdes.2017.12.015 |
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The Consortium for Advanced Simulation of Light Water Reactors (CASL) aims to provide high-fidelity multiphysics simulations of light water nuclear reactors. To accomplish this, CASL is developing the Virtual Environment for Reactor Applications (VERA), which is a suite of code packages for thermal hydraulics, neutron transport, fuel performance, and coolant chemistry. As VERA continues to grow and expand, there has been an increased focus on incorporating fuel performance analysis methods. One of the primary goals of CASL is to estimate local cladding failure probability through pellet-clad interaction, which consists of both pellet-clad mechanical interaction (PCMI) and stress corrosion cracking. Estimating clad failure is important to preventing release of fission products to the primary system and accurate estimates could prove useful in establishing less conservative power ramp rates or when considering load-follow operations.
While this capability is being pursued through several different approaches, the procedure presented in this article focuses on running independent fuel performance calculations with BISON using a file-based one-way coupling based on multicycle output data from high fidelity, pin-resolved coupled neutron transport–thermal hydraulics simulations. This type of approach is consistent with traditional fuel performance analysis methods, which are typically separate from core simulation analyses. A more tightly coupled approach is currently being developed, which is the ultimate target application in CASL.
Recent work simulating 12 cycles of Watts Bar Unit 1 with VERA core simulator are capitalized upon, and quarter-core BISON results for parameters of interest to PCMI (maximum centerline fuel temperature, maximum clad hoop stress, and minimum gap size) are presented for Cycles 1–3. Based on these results, this capability demonstrates its value and how it could be used as a screening tool for gathering insight into PCMI, singling out limiting rods for further, more detailed analysis.</description><identifier>ISSN: 0029-5493</identifier><identifier>EISSN: 1872-759X</identifier><identifier>DOI: 10.1016/j.nucengdes.2017.12.015</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>BISON ; CASL ; Cladding ; Consortia ; Data processing ; Fission products ; Fluid dynamics ; Fluid flow ; Fuel performance ; Hoop stress ; Hydraulics ; Light water reactors ; Nuclear fuels ; Nuclear reactors ; PCMI ; Reactors ; Rods ; Screening ; Simulation ; Stress corrosion ; Stress corrosion cracking ; Transport ; VERA ; Virtual environments</subject><ispartof>Nuclear engineering and design, 2018-02, Vol.327, p.172-186</ispartof><rights>2017 Elsevier B.V.</rights><rights>Copyright Elsevier BV Feb 2018</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c450t-c4c112a14265e422102deb9e4bc9757b7667ce2aab543f2336bd1f1eae7959613</citedby><cites>FETCH-LOGICAL-c450t-c4c112a14265e422102deb9e4bc9757b7667ce2aab543f2336bd1f1eae7959613</cites><orcidid>0000-0003-3653-3880 ; 0000-0002-0120-9928 ; 0000-0002-8487-8077 ; 0000-0002-5999-2978</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0029549317305873$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3537,27901,27902,65534</link.rule.ids></links><search><creatorcontrib>Stimpson, Shane</creatorcontrib><creatorcontrib>Powers, Jeffrey</creatorcontrib><creatorcontrib>Clarno, Kevin</creatorcontrib><creatorcontrib>Pawlowski, Roger</creatorcontrib><creatorcontrib>Gardner, Russell</creatorcontrib><creatorcontrib>Novascone, Stephen</creatorcontrib><creatorcontrib>Gamble, Kyle</creatorcontrib><creatorcontrib>Williamson, Richard</creatorcontrib><title>Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3</title><title>Nuclear engineering and design</title><description>•A file-based, one-way coupling with BISON fuel performance simulations is presented.•This capability can be used as a screen tool for pellet clad interaction.•Allows for insight into the fuel performance physics through VERA simulations.•Cycles 1–3 of Watts Bar Nuclear Unit 1 are highlighted.
The Consortium for Advanced Simulation of Light Water Reactors (CASL) aims to provide high-fidelity multiphysics simulations of light water nuclear reactors. To accomplish this, CASL is developing the Virtual Environment for Reactor Applications (VERA), which is a suite of code packages for thermal hydraulics, neutron transport, fuel performance, and coolant chemistry. As VERA continues to grow and expand, there has been an increased focus on incorporating fuel performance analysis methods. One of the primary goals of CASL is to estimate local cladding failure probability through pellet-clad interaction, which consists of both pellet-clad mechanical interaction (PCMI) and stress corrosion cracking. Estimating clad failure is important to preventing release of fission products to the primary system and accurate estimates could prove useful in establishing less conservative power ramp rates or when considering load-follow operations.
While this capability is being pursued through several different approaches, the procedure presented in this article focuses on running independent fuel performance calculations with BISON using a file-based one-way coupling based on multicycle output data from high fidelity, pin-resolved coupled neutron transport–thermal hydraulics simulations. This type of approach is consistent with traditional fuel performance analysis methods, which are typically separate from core simulation analyses. A more tightly coupled approach is currently being developed, which is the ultimate target application in CASL.
Recent work simulating 12 cycles of Watts Bar Unit 1 with VERA core simulator are capitalized upon, and quarter-core BISON results for parameters of interest to PCMI (maximum centerline fuel temperature, maximum clad hoop stress, and minimum gap size) are presented for Cycles 1–3. Based on these results, this capability demonstrates its value and how it could be used as a screening tool for gathering insight into PCMI, singling out limiting rods for further, more detailed analysis.</description><subject>BISON</subject><subject>CASL</subject><subject>Cladding</subject><subject>Consortia</subject><subject>Data processing</subject><subject>Fission products</subject><subject>Fluid dynamics</subject><subject>Fluid flow</subject><subject>Fuel performance</subject><subject>Hoop stress</subject><subject>Hydraulics</subject><subject>Light water reactors</subject><subject>Nuclear fuels</subject><subject>Nuclear reactors</subject><subject>PCMI</subject><subject>Reactors</subject><subject>Rods</subject><subject>Screening</subject><subject>Simulation</subject><subject>Stress corrosion</subject><subject>Stress corrosion cracking</subject><subject>Transport</subject><subject>VERA</subject><subject>Virtual environments</subject><issn>0029-5493</issn><issn>1872-759X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNqFkE1OwzAQhS0EEqVwBiyxJcHj_LhZloo_qRIIUWBnOc6kuEqdYjtI3XEHbshJSFTEllnMbOa9mfcRcgosBgb5xSq2nUa7rNDHnIGIgccMsj0ygongkciK130yYowXUZYWySE58n7Fhir4iKgHbBoMkW5URdeo35Q1WjXU2IBO6WBaS712iNbYJe380J-vHqdUbTaNwYqGlr6oEDy9VI4urAkUzulsqxv0FL4_v5JjclCrxuPJ7xyTxfXV0-w2mt_f3M2m80inGesfSDUAV5DyPMOUc2C8wrLAtNSFyEQp8lxo5EqVWZrUPEnysoIaUKEosiKHZEzOdr4b17536INctZ2z_UnJ-_ApCEgm_ZbYbWnXeu-wlhtn1sptJTA58JQr-cdTDjwlcNnz7JXTnRL7EB8GnfTaoNVYGYc6yKo1_3r8ALewgns</recordid><startdate>20180201</startdate><enddate>20180201</enddate><creator>Stimpson, Shane</creator><creator>Powers, Jeffrey</creator><creator>Clarno, Kevin</creator><creator>Pawlowski, Roger</creator><creator>Gardner, Russell</creator><creator>Novascone, Stephen</creator><creator>Gamble, Kyle</creator><creator>Williamson, Richard</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><orcidid>https://orcid.org/0000-0003-3653-3880</orcidid><orcidid>https://orcid.org/0000-0002-0120-9928</orcidid><orcidid>https://orcid.org/0000-0002-8487-8077</orcidid><orcidid>https://orcid.org/0000-0002-5999-2978</orcidid></search><sort><creationdate>20180201</creationdate><title>Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3</title><author>Stimpson, Shane ; Powers, Jeffrey ; Clarno, Kevin ; Pawlowski, Roger ; Gardner, Russell ; Novascone, Stephen ; Gamble, Kyle ; Williamson, Richard</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c450t-c4c112a14265e422102deb9e4bc9757b7667ce2aab543f2336bd1f1eae7959613</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>BISON</topic><topic>CASL</topic><topic>Cladding</topic><topic>Consortia</topic><topic>Data processing</topic><topic>Fission products</topic><topic>Fluid dynamics</topic><topic>Fluid flow</topic><topic>Fuel performance</topic><topic>Hoop stress</topic><topic>Hydraulics</topic><topic>Light water reactors</topic><topic>Nuclear fuels</topic><topic>Nuclear reactors</topic><topic>PCMI</topic><topic>Reactors</topic><topic>Rods</topic><topic>Screening</topic><topic>Simulation</topic><topic>Stress corrosion</topic><topic>Stress corrosion cracking</topic><topic>Transport</topic><topic>VERA</topic><topic>Virtual environments</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Stimpson, Shane</creatorcontrib><creatorcontrib>Powers, Jeffrey</creatorcontrib><creatorcontrib>Clarno, Kevin</creatorcontrib><creatorcontrib>Pawlowski, Roger</creatorcontrib><creatorcontrib>Gardner, Russell</creatorcontrib><creatorcontrib>Novascone, Stephen</creatorcontrib><creatorcontrib>Gamble, Kyle</creatorcontrib><creatorcontrib>Williamson, Richard</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>Stimpson, Shane</au><au>Powers, Jeffrey</au><au>Clarno, Kevin</au><au>Pawlowski, Roger</au><au>Gardner, Russell</au><au>Novascone, Stephen</au><au>Gamble, Kyle</au><au>Williamson, Richard</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3</atitle><jtitle>Nuclear engineering and design</jtitle><date>2018-02-01</date><risdate>2018</risdate><volume>327</volume><spage>172</spage><epage>186</epage><pages>172-186</pages><issn>0029-5493</issn><eissn>1872-759X</eissn><abstract>•A file-based, one-way coupling with BISON fuel performance simulations is presented.•This capability can be used as a screen tool for pellet clad interaction.•Allows for insight into the fuel performance physics through VERA simulations.•Cycles 1–3 of Watts Bar Nuclear Unit 1 are highlighted.
The Consortium for Advanced Simulation of Light Water Reactors (CASL) aims to provide high-fidelity multiphysics simulations of light water nuclear reactors. To accomplish this, CASL is developing the Virtual Environment for Reactor Applications (VERA), which is a suite of code packages for thermal hydraulics, neutron transport, fuel performance, and coolant chemistry. As VERA continues to grow and expand, there has been an increased focus on incorporating fuel performance analysis methods. One of the primary goals of CASL is to estimate local cladding failure probability through pellet-clad interaction, which consists of both pellet-clad mechanical interaction (PCMI) and stress corrosion cracking. Estimating clad failure is important to preventing release of fission products to the primary system and accurate estimates could prove useful in establishing less conservative power ramp rates or when considering load-follow operations.
While this capability is being pursued through several different approaches, the procedure presented in this article focuses on running independent fuel performance calculations with BISON using a file-based one-way coupling based on multicycle output data from high fidelity, pin-resolved coupled neutron transport–thermal hydraulics simulations. This type of approach is consistent with traditional fuel performance analysis methods, which are typically separate from core simulation analyses. A more tightly coupled approach is currently being developed, which is the ultimate target application in CASL.
Recent work simulating 12 cycles of Watts Bar Unit 1 with VERA core simulator are capitalized upon, and quarter-core BISON results for parameters of interest to PCMI (maximum centerline fuel temperature, maximum clad hoop stress, and minimum gap size) are presented for Cycles 1–3. Based on these results, this capability demonstrates its value and how it could be used as a screening tool for gathering insight into PCMI, singling out limiting rods for further, more detailed analysis.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.nucengdes.2017.12.015</doi><tpages>15</tpages><orcidid>https://orcid.org/0000-0003-3653-3880</orcidid><orcidid>https://orcid.org/0000-0002-0120-9928</orcidid><orcidid>https://orcid.org/0000-0002-8487-8077</orcidid><orcidid>https://orcid.org/0000-0002-5999-2978</orcidid><oa>free_for_read</oa></addata></record> |
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subjects | BISON CASL Cladding Consortia Data processing Fission products Fluid dynamics Fluid flow Fuel performance Hoop stress Hydraulics Light water reactors Nuclear fuels Nuclear reactors PCMI Reactors Rods Screening Simulation Stress corrosion Stress corrosion cracking Transport VERA Virtual environments |
title | Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3 |
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