Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method
The SACOS code is thermal-hydraulic subchannel analysis code designed to meet steady-state conditions and operational transients in different types of reactor cores. It uses a homogeneous flow or drift-flux model to simulate single-phase and two-phase flow characteristics. In order to achieve a more...
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Veröffentlicht in: | Progress in nuclear energy (New series) 2021-04, Vol.134, p.103671, Article 103671 |
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description | The SACOS code is thermal-hydraulic subchannel analysis code designed to meet steady-state conditions and operational transients in different types of reactor cores. It uses a homogeneous flow or drift-flux model to simulate single-phase and two-phase flow characteristics. In order to achieve a more refined two-phase flow modeling for LWR cores, a new eight-equation two-fluid based analysis module of SACOS is developed in this study. The phasic equations for mass continuity, momentum, and energy are spatially discretized by the finite volume method (FVM) with a staggered grid structure. To reduce numerical diffusion and improve numerical accuracy, the high-resolution scheme with nonlinear flux limiter is implemented. The code assessment is performed with linear advection flow problem and the preliminary code validation is presented by comparing with the experimental results of Weiss 14 × 14 blockage test, CNEN 4 × 4 mixing test, Studsvik 3 × 3 mixing test, and ISPRA 4 × 4 mixing test covering single/two-phase and unheated/heated conditions. The application of SACOS implies that the code can be used to model and perform assembly-level core safety analysis with visualization capabilities for hexagonal and rectangular geometry.
Development of a two-fluid based thermal-hydraulic subchannel analysis code and its application. [Display omitted]
•A new eight-equation two-fluid based analysis module of SACOS is developed.•The high-resolution scheme with nonlinear flux limiter is implemented into code.•The validity of the higher-order scheme is verified with linear advection flow problem.•The two-fluid model is validated based on reported bundle experiments. |
doi_str_mv | 10.1016/j.pnucene.2021.103671 |
format | Article |
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Development of a two-fluid based thermal-hydraulic subchannel analysis code and its application. [Display omitted]
•A new eight-equation two-fluid based analysis module of SACOS is developed.•The high-resolution scheme with nonlinear flux limiter is implemented into code.•The validity of the higher-order scheme is verified with linear advection flow problem.•The two-fluid model is validated based on reported bundle experiments.</description><identifier>ISSN: 0149-1970</identifier><identifier>EISSN: 1878-4224</identifier><identifier>DOI: 10.1016/j.pnucene.2021.103671</identifier><language>eng</language><publisher>Oxford: Elsevier Ltd</publisher><subject>Finite element analysis ; Finite volume method ; Flow characteristics ; Fluid dynamics ; Heat transfer ; High resolution ; High-resolution scheme ; Hydraulics ; Light water reactors ; Mathematical models ; Mixing tests ; Nuclear engineering ; Nuclear safety ; Numerical analysis ; Numerical methods ; Preliminary assessment and validation ; Reactor core thermal-hydraulics ; Reactor cores ; SACOS ; Studies ; Two phase flow ; Two-fluid model</subject><ispartof>Progress in nuclear energy (New series), 2021-04, Vol.134, p.103671, Article 103671</ispartof><rights>2021 Elsevier Ltd</rights><rights>Copyright Elsevier BV Apr 2021</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c337t-6cac65e03d06abb86ea826dcc85b0880532f84cff6653254e093be6bd0688be83</citedby><cites>FETCH-LOGICAL-c337t-6cac65e03d06abb86ea826dcc85b0880532f84cff6653254e093be6bd0688be83</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0149197021000421$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,776,780,3536,27903,27904,65309</link.rule.ids></links><search><creatorcontrib>Gui, Minyang</creatorcontrib><creatorcontrib>Tian, Wenxi</creatorcontrib><creatorcontrib>Wu, Di</creatorcontrib><creatorcontrib>Chen, Ronghua</creatorcontrib><creatorcontrib>Wang, Mingjun</creatorcontrib><creatorcontrib>Su, G.H.</creatorcontrib><title>Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method</title><title>Progress in nuclear energy (New series)</title><description>The SACOS code is thermal-hydraulic subchannel analysis code designed to meet steady-state conditions and operational transients in different types of reactor cores. It uses a homogeneous flow or drift-flux model to simulate single-phase and two-phase flow characteristics. In order to achieve a more refined two-phase flow modeling for LWR cores, a new eight-equation two-fluid based analysis module of SACOS is developed in this study. The phasic equations for mass continuity, momentum, and energy are spatially discretized by the finite volume method (FVM) with a staggered grid structure. To reduce numerical diffusion and improve numerical accuracy, the high-resolution scheme with nonlinear flux limiter is implemented. The code assessment is performed with linear advection flow problem and the preliminary code validation is presented by comparing with the experimental results of Weiss 14 × 14 blockage test, CNEN 4 × 4 mixing test, Studsvik 3 × 3 mixing test, and ISPRA 4 × 4 mixing test covering single/two-phase and unheated/heated conditions. The application of SACOS implies that the code can be used to model and perform assembly-level core safety analysis with visualization capabilities for hexagonal and rectangular geometry.
Development of a two-fluid based thermal-hydraulic subchannel analysis code and its application. [Display omitted]
•A new eight-equation two-fluid based analysis module of SACOS is developed.•The high-resolution scheme with nonlinear flux limiter is implemented into code.•The validity of the higher-order scheme is verified with linear advection flow problem.•The two-fluid model is validated based on reported bundle experiments.</description><subject>Finite element analysis</subject><subject>Finite volume method</subject><subject>Flow characteristics</subject><subject>Fluid dynamics</subject><subject>Heat transfer</subject><subject>High resolution</subject><subject>High-resolution scheme</subject><subject>Hydraulics</subject><subject>Light water reactors</subject><subject>Mathematical models</subject><subject>Mixing tests</subject><subject>Nuclear engineering</subject><subject>Nuclear safety</subject><subject>Numerical analysis</subject><subject>Numerical methods</subject><subject>Preliminary assessment and validation</subject><subject>Reactor core thermal-hydraulics</subject><subject>Reactor cores</subject><subject>SACOS</subject><subject>Studies</subject><subject>Two phase flow</subject><subject>Two-fluid model</subject><issn>0149-1970</issn><issn>1878-4224</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><recordid>eNqFkEtLxDAUhYMoOD5-ghBw3TFJmzSzEhmfILjRdUiTW5shTWaSVJl_b2Xcu7qXyzmHez6ErihZUkLFzWa5DZOBAEtGGJ1vtWjpEVpQ2cqqYaw5RgtCm1VFVy05RWc5bwihLeV8gXb38AU-bkcIBccea1y-Y9X7yVnc6QwWlwHSqH017G3Sk3cG56kzgw4BPNZB-312GZtoAX-7MuDBfQ5Vghz9VFwMOEwjJGe0xyOUIdoLdNJrn-Hyb56jj8eH9_Vz9fr29LK-e61MXbelEkYbwYHUlgjddVKAlkxYYyTviJSE16yXjel7IeaVN0BWdQeim-VSdiDrc3R9yN2muJsgF7WJU5r_zYpxJlndMC5mFT-oTIo5J-jVNrlRp72iRP3SVRv1R1f90lUHurPv9uCDucKXg6SycRAMWJfAFGWj-yfhByJuh_Y</recordid><startdate>202104</startdate><enddate>202104</enddate><creator>Gui, Minyang</creator><creator>Tian, Wenxi</creator><creator>Wu, Di</creator><creator>Chen, Ronghua</creator><creator>Wang, Mingjun</creator><creator>Su, G.H.</creator><general>Elsevier Ltd</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope></search><sort><creationdate>202104</creationdate><title>Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method</title><author>Gui, Minyang ; Tian, Wenxi ; Wu, Di ; Chen, Ronghua ; Wang, Mingjun ; Su, G.H.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c337t-6cac65e03d06abb86ea826dcc85b0880532f84cff6653254e093be6bd0688be83</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Finite element analysis</topic><topic>Finite volume method</topic><topic>Flow characteristics</topic><topic>Fluid dynamics</topic><topic>Heat transfer</topic><topic>High resolution</topic><topic>High-resolution scheme</topic><topic>Hydraulics</topic><topic>Light water reactors</topic><topic>Mathematical models</topic><topic>Mixing tests</topic><topic>Nuclear engineering</topic><topic>Nuclear safety</topic><topic>Numerical analysis</topic><topic>Numerical methods</topic><topic>Preliminary assessment and validation</topic><topic>Reactor core thermal-hydraulics</topic><topic>Reactor cores</topic><topic>SACOS</topic><topic>Studies</topic><topic>Two phase flow</topic><topic>Two-fluid model</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Gui, Minyang</creatorcontrib><creatorcontrib>Tian, Wenxi</creatorcontrib><creatorcontrib>Wu, Di</creatorcontrib><creatorcontrib>Chen, Ronghua</creatorcontrib><creatorcontrib>Wang, Mingjun</creatorcontrib><creatorcontrib>Su, G.H.</creatorcontrib><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><jtitle>Progress in nuclear energy (New series)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Gui, Minyang</au><au>Tian, Wenxi</au><au>Wu, Di</au><au>Chen, Ronghua</au><au>Wang, Mingjun</au><au>Su, G.H.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method</atitle><jtitle>Progress in nuclear energy (New series)</jtitle><date>2021-04</date><risdate>2021</risdate><volume>134</volume><spage>103671</spage><pages>103671-</pages><artnum>103671</artnum><issn>0149-1970</issn><eissn>1878-4224</eissn><abstract>The SACOS code is thermal-hydraulic subchannel analysis code designed to meet steady-state conditions and operational transients in different types of reactor cores. It uses a homogeneous flow or drift-flux model to simulate single-phase and two-phase flow characteristics. In order to achieve a more refined two-phase flow modeling for LWR cores, a new eight-equation two-fluid based analysis module of SACOS is developed in this study. The phasic equations for mass continuity, momentum, and energy are spatially discretized by the finite volume method (FVM) with a staggered grid structure. To reduce numerical diffusion and improve numerical accuracy, the high-resolution scheme with nonlinear flux limiter is implemented. The code assessment is performed with linear advection flow problem and the preliminary code validation is presented by comparing with the experimental results of Weiss 14 × 14 blockage test, CNEN 4 × 4 mixing test, Studsvik 3 × 3 mixing test, and ISPRA 4 × 4 mixing test covering single/two-phase and unheated/heated conditions. The application of SACOS implies that the code can be used to model and perform assembly-level core safety analysis with visualization capabilities for hexagonal and rectangular geometry.
Development of a two-fluid based thermal-hydraulic subchannel analysis code and its application. [Display omitted]
•A new eight-equation two-fluid based analysis module of SACOS is developed.•The high-resolution scheme with nonlinear flux limiter is implemented into code.•The validity of the higher-order scheme is verified with linear advection flow problem.•The two-fluid model is validated based on reported bundle experiments.</abstract><cop>Oxford</cop><pub>Elsevier Ltd</pub><doi>10.1016/j.pnucene.2021.103671</doi></addata></record> |
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subjects | Finite element analysis Finite volume method Flow characteristics Fluid dynamics Heat transfer High resolution High-resolution scheme Hydraulics Light water reactors Mathematical models Mixing tests Nuclear engineering Nuclear safety Numerical analysis Numerical methods Preliminary assessment and validation Reactor core thermal-hydraulics Reactor cores SACOS Studies Two phase flow Two-fluid model |
title | Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method |
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