Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor
A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic design. The iso-kinetic sampling method has been...
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Published in | Nuclear engineering and technology Vol. 48; no. 2; pp. 376 - 385 |
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Main Authors | , , , , , |
Format | Journal Article |
Language | English |
Published |
Elsevier B.V
01.04.2016
Elsevier 한국원자력학회 |
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Online Access | Get full text |
ISSN | 1738-5733 2234-358X |
DOI | 10.1016/j.net.2015.12.013 |
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Abstract | A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic design. The iso-kinetic sampling method has been adopted to measure the flow rate at subchannels, and newly designed sampling probes which preserve the flow area of subchannels have been devised. Experimental tests have been performed at 20–115% of the nominal flow rate and 60°C (equivalent to Re ∼ 37,100) at the inlet of the test rig. The pressure loss data in three measured subchannels were almost identical regardless of the subchannel locations. The flow rate at each type of subchannel was identified and the flow split factors were evaluated from the measured data. The predicted correlations and the computational fluid dynamics results agreed reasonably with the experimental data. |
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AbstractList | A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic design.
The iso-kinetic sampling method has been adopted to measure the flow rate at subchannels, and newly designed sampling probes which preserve the flow area of subchannels have been devised. Experimental tests have been performed at 20-115% of the nominal flow rate and 60℃ (equivalent to Re ~ 37,100) at the inlet of the test rig. The pressure loss data in three measured subchannels were almost identical regardless of the subchannel locations. The flow rate at each type of subchannel was identified and the flow split factors were evaluated from the measured data. The predicted correlations and the computational fluid dynamics results agreed reasonably with the experimental data. KCI Citation Count: 11 A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic design. The iso-kinetic sampling method has been adopted to measure the flow rate at subchannels, and newly designed sampling probes which preserve the flow area of subchannels have been devised. Experimental tests have been performed at 20–115% of the nominal flow rate and 60°C (equivalent to Re ∼ 37,100) at the inlet of the test rig. The pressure loss data in three measured subchannels were almost identical regardless of the subchannel locations. The flow rate at each type of subchannel was identified and the flow split factors were evaluated from the measured data. The predicted correlations and the computational fluid dynamics results agreed reasonably with the experimental data. |
Author | Choi, Hae Seob Kim, Hyungmo Euh, Dong-Jin Lee, Hyeong-Yeon Chang, Seok-Kyu Choi, Sun Rock |
Author_xml | – sequence: 1 givenname: Seok-Kyu surname: Chang fullname: Chang, Seok-Kyu – sequence: 2 givenname: Dong-Jin surname: Euh fullname: Euh, Dong-Jin email: djeuh@kaeri.re.kr – sequence: 3 givenname: Hae Seob surname: Choi fullname: Choi, Hae Seob – sequence: 4 givenname: Hyungmo surname: Kim fullname: Kim, Hyungmo – sequence: 5 givenname: Sun Rock surname: Choi fullname: Choi, Sun Rock – sequence: 6 givenname: Hyeong-Yeon surname: Lee fullname: Lee, Hyeong-Yeon |
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Cites_doi | 10.1016/0029-5493(75)90198-3 10.13182/NSE67-A18661 10.1016/j.nucengdes.2008.06.024 10.1016/0029-5493(77)90042-5 10.13182/NT73-A31250 10.1016/0029-5493(75)90076-X 10.1016/0029-5493(80)90038-2 10.1016/0029-5493(72)90059-3 10.1016/0029-5493(72)90060-X 10.1016/0029-5493(86)90249-9 10.1016/j.nucengdes.2013.12.003 |
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Keywords | Wire-wrapped Subchannel Analysis Code Subchannel Rod Bundle Split Factor Pressure Loss Iso-kinetic Sampling |
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References | Baglietto (bib13) 2006 Rehme, Trippe (bib6) 1980; 62 CD-adapco (bib15) 2011 Rowe (bib16) 1970 Rehme (bib7) 1973; 17 Lorenz, Ginsberg (bib5) 1977; 40 Cheng (bib9) 1984 Kim, Choi (bib1) 2011 Hetsroni (bib12) 1967; 28 Chen, Todreas, Nguyen (bib11) 2014; 267 Ginsberg (bib2) 1972; 22 Khan, Rohsenow, Sonin, Todreas (bib3) 1975; 35 Khan, Rohsenow, Sonin, Todreas (bib4) 1975; 35 Cheng, Todreas (bib10) 1986; 92 Novendstern (bib14) 1972; 22 Bubelis, Schikorr (bib8) 2008; 238 Novendstern (10.1016/j.net.2015.12.013_bib14) 1972; 22 Cheng (10.1016/j.net.2015.12.013_bib10) 1986; 92 Lorenz (10.1016/j.net.2015.12.013_bib5) 1977; 40 Kim (10.1016/j.net.2015.12.013_bib1) 2011 Chen (10.1016/j.net.2015.12.013_bib11) 2014; 267 Khan (10.1016/j.net.2015.12.013_bib4) 1975; 35 Bubelis (10.1016/j.net.2015.12.013_bib8) 2008; 238 Baglietto (10.1016/j.net.2015.12.013_bib13) 2006 Khan (10.1016/j.net.2015.12.013_bib3) 1975; 35 Rehme (10.1016/j.net.2015.12.013_bib6) 1980; 62 Rehme (10.1016/j.net.2015.12.013_bib7) 1973; 17 Cheng (10.1016/j.net.2015.12.013_bib9) 1984 CD-adapco (10.1016/j.net.2015.12.013_bib15) 2011 Rowe (10.1016/j.net.2015.12.013_bib16) 1970 Ginsberg (10.1016/j.net.2015.12.013_bib2) 1972; 22 Hetsroni (10.1016/j.net.2015.12.013_bib12) 1967; 28 |
References_xml | – volume: 35 start-page: 1 year: 1975 end-page: 12 ident: bib3 article-title: A porous body model for predicting temperature distribution in wire-wrapped rod assemblies operating in forced convection publication-title: Nucl. Eng. Design – volume: 40 start-page: 315 year: 1977 end-page: 326 ident: bib5 article-title: Coolant mixing and subchannel velocities in an LMFBR fuel assembly publication-title: Nucl. Eng. Design – volume: 28 start-page: 1 year: 1967 end-page: 11 ident: bib12 article-title: Use of hydraulic models in nuclear reactor design publication-title: Nucl. Sci. Eng. – year: 2011 ident: bib15 article-title: ‘STAR-CCM+’ Code Manual, Version 7.06 – volume: 35 start-page: 199 year: 1975 end-page: 211 ident: bib4 article-title: A porous body model for predicting temperature distribution in wire-wrapped rod assemblies operating in combined forced and free convection publication-title: Nucl. Eng. Design – volume: 238 start-page: 3299 year: 2008 end-page: 3320 ident: bib8 article-title: Review and proposal for best-fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations publication-title: Nucl. Eng. Design – year: 2011 ident: bib1 article-title: Establishment of Test Specifications of Flow Characteristics in Subchannels – volume: 62 start-page: 349 year: 1980 end-page: 359 ident: bib6 article-title: Pressure drop and velocity distribution in rod bundles with spacer grids publication-title: Nucl. Eng. Design – volume: 17 start-page: 15 year: 1973 end-page: 23 ident: bib7 article-title: Pressure drop correlations for fuel element spacers publication-title: Nucl. Technol. – volume: 22 start-page: 19 year: 1972 end-page: 27 ident: bib14 article-title: Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrapped spacer system publication-title: Nucl. Eng. Design – volume: 22 start-page: 28 year: 1972 end-page: 42 ident: bib2 article-title: Forced–flow interchannel mixing model for fuel rod assemblies utilizing a helical wire-wrap spacer system publication-title: Nucl. Eng. Design – year: 2006 ident: bib13 article-title: Improved Anisotropic k- – volume: 267 start-page: 109 year: 2014 end-page: 131 ident: bib11 article-title: Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles publication-title: Nucl. Eng. Design – year: 1970 ident: bib16 article-title: COBRA-II: A Digital Computer Program for Thermal-hydraulic Subchannel Analysis of Rod Bundle Nuclear Fuel Elements – year: 1984 ident: bib9 article-title: Constitutive Correlations for Wire-wrapped Subchannel Analysis Under Forced and Mixed Convection Conditions – volume: 92 start-page: 227 year: 1986 end-page: 251 ident: bib10 article-title: Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles - bundle friction factors, subchannel friction factors and mixing parameters publication-title: Nucl. Eng. Design – volume: 35 start-page: 199 year: 1975 ident: 10.1016/j.net.2015.12.013_bib4 article-title: A porous body model for predicting temperature distribution in wire-wrapped rod assemblies operating in combined forced and free convection publication-title: Nucl. Eng. Design doi: 10.1016/0029-5493(75)90198-3 – volume: 28 start-page: 1 year: 1967 ident: 10.1016/j.net.2015.12.013_bib12 article-title: Use of hydraulic models in nuclear reactor design publication-title: Nucl. Sci. Eng. doi: 10.13182/NSE67-A18661 – year: 2006 ident: 10.1016/j.net.2015.12.013_bib13 – volume: 238 start-page: 3299 year: 2008 ident: 10.1016/j.net.2015.12.013_bib8 article-title: Review and proposal for best-fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations publication-title: Nucl. Eng. Design doi: 10.1016/j.nucengdes.2008.06.024 – volume: 40 start-page: 315 year: 1977 ident: 10.1016/j.net.2015.12.013_bib5 article-title: Coolant mixing and subchannel velocities in an LMFBR fuel assembly publication-title: Nucl. Eng. Design doi: 10.1016/0029-5493(77)90042-5 – volume: 17 start-page: 15 year: 1973 ident: 10.1016/j.net.2015.12.013_bib7 article-title: Pressure drop correlations for fuel element spacers publication-title: Nucl. Technol. doi: 10.13182/NT73-A31250 – year: 2011 ident: 10.1016/j.net.2015.12.013_bib15 – year: 2011 ident: 10.1016/j.net.2015.12.013_bib1 – volume: 35 start-page: 1 year: 1975 ident: 10.1016/j.net.2015.12.013_bib3 article-title: A porous body model for predicting temperature distribution in wire-wrapped rod assemblies operating in forced convection publication-title: Nucl. Eng. Design doi: 10.1016/0029-5493(75)90076-X – volume: 62 start-page: 349 year: 1980 ident: 10.1016/j.net.2015.12.013_bib6 article-title: Pressure drop and velocity distribution in rod bundles with spacer grids publication-title: Nucl. Eng. Design doi: 10.1016/0029-5493(80)90038-2 – volume: 22 start-page: 19 year: 1972 ident: 10.1016/j.net.2015.12.013_bib14 article-title: Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrapped spacer system publication-title: Nucl. Eng. Design doi: 10.1016/0029-5493(72)90059-3 – year: 1970 ident: 10.1016/j.net.2015.12.013_bib16 – volume: 22 start-page: 28 year: 1972 ident: 10.1016/j.net.2015.12.013_bib2 article-title: Forced–flow interchannel mixing model for fuel rod assemblies utilizing a helical wire-wrap spacer system publication-title: Nucl. Eng. Design doi: 10.1016/0029-5493(72)90060-X – volume: 92 start-page: 227 year: 1986 ident: 10.1016/j.net.2015.12.013_bib10 article-title: Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles - bundle friction factors, subchannel friction factors and mixing parameters publication-title: Nucl. Eng. Design doi: 10.1016/0029-5493(86)90249-9 – volume: 267 start-page: 109 year: 2014 ident: 10.1016/j.net.2015.12.013_bib11 article-title: Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles publication-title: Nucl. Eng. Design doi: 10.1016/j.nucengdes.2013.12.003 – year: 1984 ident: 10.1016/j.net.2015.12.013_bib9 |
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SubjectTerms | Iso-kinetic Sampling Pressure Loss Rod Bundle Split Factor Subchannel Subchannel Analysis Code Wire-wrapped 원자력공학 |
Title | Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor |
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