Numerical and experimental investigation of the water flow through PWR spacer grids

Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental an...
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Autor*in:	Higor Fabiano Pereira de Castro [verfasserIn] Guilherme Augusto Moura Vidal [verfasserIn] Tiago Augusto Santiago Vieira [verfasserIn] Vitor Vasconcelos Araújo Silva [verfasserIn] Daniel de Almeida Magalhães Campolina [verfasserIn] Graiciany de Paula Barros [verfasserIn] Rebeca Cabral Gonçalves [verfasserIn] Andre Augusto Campagnole dos Santos [verfasserIn] Maria Auxiliadora Fortini Veloso [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch ; Portugiesisch

Erschienen:	2021

Schlagwörter:	Spacer grids LDV CFD Thermo-hydraulic PWR

Übergeordnetes Werk:	In: Brazilian Journal of Radiation Sciences - Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022, 8(2021), 3A
Übergeordnetes Werk:	volume:8 ; year:2021 ; number:3A

Links:	Link aufrufen Link aufrufen Link aufrufen Journal toc

DOI / URN:	10.15392/bjrs.v8i3A.1294

Katalog-ID:	DOAJ020963106

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520			\|a Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes.
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spelling	10.15392/bjrs.v8i3A.1294 doi (DE-627)DOAJ020963106 (DE-599)DOAJ1be610a63ca240f3a888ec7be0eb260b DE-627 ger DE-627 rakwb eng por Higor Fabiano Pereira de Castro verfasserin aut Numerical and experimental investigation of the water flow through PWR spacer grids 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes. Spacer grids LDV CFD Thermo-hydraulic PWR Science Q Guilherme Augusto Moura Vidal verfasserin aut Tiago Augusto Santiago Vieira verfasserin aut Vitor Vasconcelos Araújo Silva verfasserin aut Daniel de Almeida Magalhães Campolina verfasserin aut Graiciany de Paula Barros verfasserin aut Rebeca Cabral Gonçalves verfasserin aut Andre Augusto Campagnole dos Santos verfasserin aut Maria Auxiliadora Fortini Veloso verfasserin aut In Brazilian Journal of Radiation Sciences Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022 8(2021), 3A (DE-627)1813774838 (DE-600)3130234-8 23190612 nnns volume:8 year:2021 number:3A https://doi.org/10.15392/bjrs.v8i3A.1294 kostenfrei https://doaj.org/article/1be610a63ca240f3a888ec7be0eb260b kostenfrei https://bjrs.org.br/revista/index.php/REVISTA/article/view/1294 kostenfrei https://doaj.org/toc/2319-0612 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 8 2021 3A
allfields_unstemmed	10.15392/bjrs.v8i3A.1294 doi (DE-627)DOAJ020963106 (DE-599)DOAJ1be610a63ca240f3a888ec7be0eb260b DE-627 ger DE-627 rakwb eng por Higor Fabiano Pereira de Castro verfasserin aut Numerical and experimental investigation of the water flow through PWR spacer grids 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes. Spacer grids LDV CFD Thermo-hydraulic PWR Science Q Guilherme Augusto Moura Vidal verfasserin aut Tiago Augusto Santiago Vieira verfasserin aut Vitor Vasconcelos Araújo Silva verfasserin aut Daniel de Almeida Magalhães Campolina verfasserin aut Graiciany de Paula Barros verfasserin aut Rebeca Cabral Gonçalves verfasserin aut Andre Augusto Campagnole dos Santos verfasserin aut Maria Auxiliadora Fortini Veloso verfasserin aut In Brazilian Journal of Radiation Sciences Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022 8(2021), 3A (DE-627)1813774838 (DE-600)3130234-8 23190612 nnns volume:8 year:2021 number:3A https://doi.org/10.15392/bjrs.v8i3A.1294 kostenfrei https://doaj.org/article/1be610a63ca240f3a888ec7be0eb260b kostenfrei https://bjrs.org.br/revista/index.php/REVISTA/article/view/1294 kostenfrei https://doaj.org/toc/2319-0612 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 8 2021 3A
allfieldsGer	10.15392/bjrs.v8i3A.1294 doi (DE-627)DOAJ020963106 (DE-599)DOAJ1be610a63ca240f3a888ec7be0eb260b DE-627 ger DE-627 rakwb eng por Higor Fabiano Pereira de Castro verfasserin aut Numerical and experimental investigation of the water flow through PWR spacer grids 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes. Spacer grids LDV CFD Thermo-hydraulic PWR Science Q Guilherme Augusto Moura Vidal verfasserin aut Tiago Augusto Santiago Vieira verfasserin aut Vitor Vasconcelos Araújo Silva verfasserin aut Daniel de Almeida Magalhães Campolina verfasserin aut Graiciany de Paula Barros verfasserin aut Rebeca Cabral Gonçalves verfasserin aut Andre Augusto Campagnole dos Santos verfasserin aut Maria Auxiliadora Fortini Veloso verfasserin aut In Brazilian Journal of Radiation Sciences Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022 8(2021), 3A (DE-627)1813774838 (DE-600)3130234-8 23190612 nnns volume:8 year:2021 number:3A https://doi.org/10.15392/bjrs.v8i3A.1294 kostenfrei https://doaj.org/article/1be610a63ca240f3a888ec7be0eb260b kostenfrei https://bjrs.org.br/revista/index.php/REVISTA/article/view/1294 kostenfrei https://doaj.org/toc/2319-0612 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 8 2021 3A
allfieldsSound	10.15392/bjrs.v8i3A.1294 doi (DE-627)DOAJ020963106 (DE-599)DOAJ1be610a63ca240f3a888ec7be0eb260b DE-627 ger DE-627 rakwb eng por Higor Fabiano Pereira de Castro verfasserin aut Numerical and experimental investigation of the water flow through PWR spacer grids 2021 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes. Spacer grids LDV CFD Thermo-hydraulic PWR Science Q Guilherme Augusto Moura Vidal verfasserin aut Tiago Augusto Santiago Vieira verfasserin aut Vitor Vasconcelos Araújo Silva verfasserin aut Daniel de Almeida Magalhães Campolina verfasserin aut Graiciany de Paula Barros verfasserin aut Rebeca Cabral Gonçalves verfasserin aut Andre Augusto Campagnole dos Santos verfasserin aut Maria Auxiliadora Fortini Veloso verfasserin aut In Brazilian Journal of Radiation Sciences Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR), 2022 8(2021), 3A (DE-627)1813774838 (DE-600)3130234-8 23190612 nnns volume:8 year:2021 number:3A https://doi.org/10.15392/bjrs.v8i3A.1294 kostenfrei https://doaj.org/article/1be610a63ca240f3a888ec7be0eb260b kostenfrei https://bjrs.org.br/revista/index.php/REVISTA/article/view/1294 kostenfrei https://doaj.org/toc/2319-0612 Journal toc kostenfrei GBV_USEFLAG_A SYSFLAG_A GBV_DOAJ GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_39 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_95 GBV_ILN_105 GBV_ILN_110 GBV_ILN_151 GBV_ILN_161 GBV_ILN_170 GBV_ILN_206 GBV_ILN_213 GBV_ILN_230 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_2014 GBV_ILN_4012 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4249 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4367 GBV_ILN_4700 AR 8 2021 3A
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author	Higor Fabiano Pereira de Castro
spellingShingle	Higor Fabiano Pereira de Castro misc Spacer grids misc LDV misc CFD misc Thermo-hydraulic misc PWR misc Science misc Q Numerical and experimental investigation of the water flow through PWR spacer grids
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topic_title	Numerical and experimental investigation of the water flow through PWR spacer grids Spacer grids LDV CFD Thermo-hydraulic PWR
topic	misc Spacer grids misc LDV misc CFD misc Thermo-hydraulic misc PWR misc Science misc Q
topic_unstemmed	misc Spacer grids misc LDV misc CFD misc Thermo-hydraulic misc PWR misc Science misc Q
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title	Numerical and experimental investigation of the water flow through PWR spacer grids
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title_full	Numerical and experimental investigation of the water flow through PWR spacer grids
author_sort	Higor Fabiano Pereira de Castro
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author_browse	Higor Fabiano Pereira de Castro Guilherme Augusto Moura Vidal Tiago Augusto Santiago Vieira Vitor Vasconcelos Araújo Silva Daniel de Almeida Magalhães Campolina Graiciany de Paula Barros Rebeca Cabral Gonçalves Andre Augusto Campagnole dos Santos Maria Auxiliadora Fortini Veloso
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title_sort	numerical and experimental investigation of the water flow through pwr spacer grids
title_auth	Numerical and experimental investigation of the water flow through PWR spacer grids
abstract	Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes.
abstractGer	Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes.
abstract_unstemmed	Spacer grids are one of main components of a Pressurized Water Reactor (PWR) fuel assembly. They are able to improve heat transfer from rod bundles to the water flow by increasing turbulence and mixture of this flow. On the other hand the pressure drop increases because spacer grids. Experimental and Computational Fluid Dynamics (CFD) analysis have been used to understand how spacer grids affect the water flow. This analysis is important to improve spacer grids thermal-hydraulic performance. This paper aims to investigate numerically and experimentally the water flow through PWR spacer grids. The numerical and experimental procedures have been developed for a 5x5 rod bundle with spacer grids at the Nuclear Technology Development Center (CDTN) in Belo Horizonte, Brazil. At CDTN, measurements of the velocity components are acquired with a 2D LDV (Laser Doppler Velocimetry) system and the numerical results are obtained using ANSYS CFX code. The measurements are obtained at one height downstream from a spacer grid and compared to CFD simulations for a flow rate at Reynolds number of 5.4x104 . Results show good agreement between both methodologies. The great repeatability and low experimental uncertainty evaluated (< 1.24%) in this work can be used to validate other CFD codes.
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title_short	Numerical and experimental investigation of the water flow through PWR spacer grids
url	https://doi.org/10.15392/bjrs.v8i3A.1294 https://doaj.org/article/1be610a63ca240f3a888ec7be0eb260b https://bjrs.org.br/revista/index.php/REVISTA/article/view/1294 https://doaj.org/toc/2319-0612
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author2	Guilherme Augusto Moura Vidal Tiago Augusto Santiago Vieira Vitor Vasconcelos Araújo Silva Daniel de Almeida Magalhães Campolina Graiciany de Paula Barros Rebeca Cabral Gonçalves Andre Augusto Campagnole dos Santos Maria Auxiliadora Fortini Veloso
author2Str	Guilherme Augusto Moura Vidal Tiago Augusto Santiago Vieira Vitor Vasconcelos Araújo Silva Daniel de Almeida Magalhães Campolina Graiciany de Paula Barros Rebeca Cabral Gonçalves Andre Augusto Campagnole dos Santos Maria Auxiliadora Fortini Veloso
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doi_str	10.15392/bjrs.v8i3A.1294
up_date	2024-07-03T18:03:12.500Z
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Numerical and experimental investigation of the water flow through PWR spacer grids

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