Deflection predictions of involute-shaped fuel plates using a fully-coupled numerical approach

This paper describes the modeling and simulation of fluid structure interactions (FSI) of involute-shaped fuel plates used in nuclear research reactors. We believe this to be the first time that this type of application is described in the literature using a fully-coupled, and monolithic, finite ele...

Full description

Saved in:
Bibliographic Details
Published in:Annals of nuclear energy Vol. 130; no. C; pp. 184 - 191
Main Authors: Curtis, Franklin G., Freels, James D., Ekici, Kivanc
Format: Journal Article
Language:English
Published: United States Elsevier Ltd 01-08-2019
Elsevier
Subjects:
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Abstract This paper describes the modeling and simulation of fluid structure interactions (FSI) of involute-shaped fuel plates used in nuclear research reactors. We believe this to be the first time that this type of application is described in the literature using a fully-coupled, and monolithic, finite element approach. The simulations are validated against plate deflection data for the conceptual design of the Advanced Neutron Source Reactor (ANSR), which was envisioned to be the world’s most powerful nuclear research reactor for neutron scattering and other applications, but was ultimately never completed. The high performance of the ANSR creates a bounding envelope for involute-shaped research reactors such as that used in the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) which is undergoing research for the conversion from highly-enriched uranium (HEU) to low-enriched uranium (LEU) fuel. As such, the findings from the present FSI analyses carried out herein for the ANSR plates provide good guidelines and inform designers what should be expected for the next generation of plates in the HFIR. It is shown herein that the current approach can accurately capture the leading-edge deflections of the involute-shaped plates and simulations can predict the ‘S-shaped’ deflection of the first mode instilling confidence in the methodology.
AbstractList This paper describes the modeling and simulation of fluid structure interactions (FSI) of involute-shaped fuel plates used in nuclear research reactors. We believe this to be the first time that this type of application is described in the literature using a fully-coupled, and monolithic, finite element approach. The simulations are validated against plate deflection data for the conceptual design of the Advanced Neutron Source Reactor (ANSR), which was envisioned to be the world’s most powerful nuclear research reactor for neutron scattering and other applications, but was ultimately never completed. The high performance of the ANSR creates a bounding envelope for involute-shaped research reactors such as that used in the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) which is undergoing research for the conversion from highly-enriched uranium (HEU) to low-enriched uranium (LEU) fuel. As such, the findings from the present FSI analyses carried out herein for the ANSR plates provide good guidelines and inform designers what should be expected for the next generation of plates in the HFIR. Furthermore it is shown herein that the current approach can accurately capture the leading-edge deflections of the involute-shaped plates and simulations can predict the ‘S-shaped’ deflection of the first mode instilling confidence in the methodology.
This paper describes the modeling and simulation of fluid structure interactions (FSI) of involute-shaped fuel plates used in nuclear research reactors. We believe this to be the first time that this type of application is described in the literature using a fully-coupled, and monolithic, finite element approach. The simulations are validated against plate deflection data for the conceptual design of the Advanced Neutron Source Reactor (ANSR), which was envisioned to be the world’s most powerful nuclear research reactor for neutron scattering and other applications, but was ultimately never completed. The high performance of the ANSR creates a bounding envelope for involute-shaped research reactors such as that used in the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) which is undergoing research for the conversion from highly-enriched uranium (HEU) to low-enriched uranium (LEU) fuel. As such, the findings from the present FSI analyses carried out herein for the ANSR plates provide good guidelines and inform designers what should be expected for the next generation of plates in the HFIR. It is shown herein that the current approach can accurately capture the leading-edge deflections of the involute-shaped plates and simulations can predict the ‘S-shaped’ deflection of the first mode instilling confidence in the methodology.
Author Freels, James D.
Ekici, Kivanc
Curtis, Franklin G.
Author_xml – sequence: 1
  givenname: Franklin G.
  surname: Curtis
  fullname: Curtis, Franklin G.
  email: curtisfg@ornl.gov
  organization: Oak Ridge National Laboratory, Oak Ridge, TN 37831, United States
– sequence: 2
  givenname: James D.
  surname: Freels
  fullname: Freels, James D.
  organization: Oak Ridge National Laboratory, Oak Ridge, TN 37831, United States
– sequence: 3
  givenname: Kivanc
  orcidid: 0000-0001-8839-5374
  surname: Ekici
  fullname: Ekici, Kivanc
  organization: The University of Tennessee, Knoxville, TN 37996, United States
BackLink https://www.osti.gov/biblio/1502600$$D View this record in Osti.gov
BookMark eNqFkM1LAzEQxYNUsK3-CcLifdfJx67dk0j9BMGLXg1pdmJT0mRJdgv9701t755mGN57w_vNyMQHj4RcU6go0OZ2Uyk_avRYMaBtBawCoGdkShd3vGQUYEKmwKEpRS3aCzJLaZMFbCHElHw_onGoBxt80Ufs7N-aimAK63fBjQOWaa167Aozoit6pwZMxZis_ylUvjm3L3UYe5cVftxitFq5QvV9DEqvL8m5US7h1WnOydfz0-fytXz_eHlbPryXmi_4UFKmsBMrumo11Zx3RsGKda3WFIXqWoUcTMMo1m2zMqJjyuiWNnc1bRe8EUzwObk55oY0WJm0HVCvdfA-V5O0BtYAZFF9FOkYUopoZB_tVsW9pCAPJOVGnkjKA0kJTGZQ2Xd_9GFusLMYDw_Q60wrHvK7YP9J-AV4JILM
CitedBy_id crossref_primary_10_1016_j_nucengdes_2023_112185
crossref_primary_10_1080_00223131_2024_2307430
crossref_primary_10_1016_j_nucengdes_2023_112616
Cites_doi 10.1115/1.3424025
10.1115/1.1286019
10.13182/NSE63-A26503
10.13182/NSE65-A18790
10.13182/NSE63-A26441
10.1016/0029-5493(69)90052-1
10.1016/0029-5493(83)90141-3
10.1007/s00466-008-0270-6
10.1016/0029-5493(68)90103-9
10.1016/0898-1221(78)90025-1
10.1016/0022-3107(69)90047-1
10.1504/IJCSM.2007.016531
10.1016/0029-5493(67)90064-7
10.1016/j.nucengdes.2008.01.010
10.1016/0022-3107(69)90048-3
10.1016/j.jfluidstructs.2009.06.002
10.1007/BF02319660
ContentType Journal Article
Copyright 2019 Elsevier Ltd
Copyright_xml – notice: 2019 Elsevier Ltd
CorporateAuthor Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
CorporateAuthor_xml – name: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
DBID AAYXX
CITATION
OTOTI
DOI 10.1016/j.anucene.2019.02.001
DatabaseName CrossRef
OSTI.GOV
DatabaseTitle CrossRef
DatabaseTitleList

DeliveryMethod fulltext_linktorsrc
Discipline Engineering
Physics
EISSN 1873-2100
EndPage 191
ExternalDocumentID 1502600
10_1016_j_anucene_2019_02_001
S0306454919300702
GroupedDBID --K
--M
-~X
.GJ
.~1
0R~
1B1
1~.
1~5
23M
4.4
457
4G.
53G
5GY
5VS
6TJ
7-5
71M
8P~
8WZ
9JM
9JN
A6W
AACTN
AAEDT
AAEDW
AAHCO
AAIAV
AAIKJ
AAKOC
AALRI
AAOAW
AAQFI
AAQXK
AARJD
AAXUO
ABFNM
ABFYP
ABJNI
ABLST
ABMAC
ABXDB
ABYKQ
ACDAQ
ACGFS
ACRLP
ADBBV
ADEZE
ADMUD
AEBSH
AEKER
AENEX
AFFNX
AFKWA
AFTJW
AFXIZ
AGHFR
AGUBO
AGYEJ
AHEUO
AHHHB
AHIDL
AIEXJ
AIKHN
AITUG
AJBFU
AJOXV
AKIFW
ALMA_UNASSIGNED_HOLDINGS
AMFUW
AMRAJ
ASPBG
AVWKF
AXJTR
AZFZN
BELTK
BKOJK
BLECG
BLXMC
CS3
EBS
EFJIC
EFLBG
EJD
EO8
EO9
EP2
EP3
FDB
FEDTE
FGOYB
FIRID
FNPLU
FYGXN
G-2
G-Q
GBLVA
HVGLF
HZ~
IHE
J1W
JARJE
KCYFY
KOM
LY6
M41
MO0
N9A
O-L
O9-
OAUVE
OZT
P-8
P-9
P2P
PC.
Q38
R2-
RIG
ROL
RPZ
SAC
SDF
SDG
SDP
SES
SEW
SPC
SPCBC
SPD
SSJ
SSR
SSZ
T5K
UHS
WUQ
~G-
AAXKI
AAYXX
AFJKZ
AKRWK
CITATION
AALMO
AAPBV
ABPIF
ABPTK
OTOTI
ID FETCH-LOGICAL-c383t-12aed4b1b9c1c33dfa0b2d9cc1e4ad9ae30f621e596bf4d2afc91675198364243
ISSN 0306-4549
IngestDate Thu May 18 22:45:35 EDT 2023
Thu Sep 26 17:27:32 EDT 2024
Fri Feb 23 02:26:48 EST 2024
IsDoiOpenAccess false
IsOpenAccess true
IsPeerReviewed true
IsScholarly true
Issue C
Keywords Thermal-hydraulics
Involute fuel plates
High flux isotope reactor
Fluid-structure interaction
Language English
LinkModel OpenURL
MergedId FETCHMERGED-LOGICAL-c383t-12aed4b1b9c1c33dfa0b2d9cc1e4ad9ae30f621e596bf4d2afc91675198364243
Notes USDOE
AC05-00OR22725
ORCID 0000-0001-8839-5374
0000000188395374
0000000251381259
OpenAccessLink http://manuscript.elsevier.com/S0306454919300702/pdf/S0306454919300702.pdf
PageCount 8
ParticipantIDs osti_scitechconnect_1502600
crossref_primary_10_1016_j_anucene_2019_02_001
elsevier_sciencedirect_doi_10_1016_j_anucene_2019_02_001
PublicationCentury 2000
PublicationDate 2019-08-01
PublicationDateYYYYMMDD 2019-08-01
PublicationDate_xml – month: 08
  year: 2019
  text: 2019-08-01
  day: 01
PublicationDecade 2010
PublicationPlace United States
PublicationPlace_xml – name: United States
PublicationTitle Annals of nuclear energy
PublicationYear 2019
Publisher Elsevier Ltd
Elsevier
Publisher_xml – name: Elsevier Ltd
– name: Elsevier
References McLain (b0145) 1967
Siman-Tov, Felde, Farquharson, McDuffee, McFee, Ruggles, Wendel, Yoder (b0205) 1997
Kane (b0100) 1962; 15
Guo, Païdoussis (b0070) 2000; 122
Tschaepe, Ruggles, Freels, Primm III (b0265) 2008
Curtis, Freels, Ekici (b0040) 2017; 10
HFIR Website, 2014. The High Flux Isotope Reactor at Oak Ridge National Laboratory, Neutron Sciences. URL
Freels, Jain (b0050) 2011
Groninger, Kane (b0060) 1963; 16
Swinson, Battiste, Luttrell, Yahr (b0230) 1993
(b0165) 2013
Smissaert (b0215) 1969; 9
Curtis, Ekici, Freels (b0035) 2013
Luttrell (b0140) 1995
Khane, Jain, Freels (b0120) 2012
Roth (b0180) 2012
Yoder, Dixon, Elkassabgi, Felde, Giles, Harrington, Morris, Nelson, Ruggles, Siman-Tov, Stovall (b0290) 1994
Cekirge, Ural (b0015) 1978; 4
Kim, Scarton (b0130) 1977; 44
Smissaert (b0210) 1968; 7
Bodey, I.T., Arimilli, R.V., Freels, J.D., 2011. Complex geometry creation and turbulent conjugate heat transfer modeling. In: 2011 COMSOL Conference. Boston.
Felde (b0045) 1992
.
COMSOL, 2016. COMSOL Multiphysics®, Version 5.2, www.comsol.com. COMSOL AB, Stockholm, Sweden.
Swinson, Battiste, Luttrell, Yahr (b0245) 1995; 35
Heil, Hazel, Boyle (b0075) 2008; 43
Chandler (b0020) 2011
Wang, Jain, Freels (b0275) 2013
Wick (b0280) 1969; 23
Morris, Wendel (b0160) 1993
Wambsganss (b0270) 1967; 5
Pavone, Scarton (b0170) 1983; 74
Freels, Bodey, Arimilli, Lowe (b0055) 2010
Swinson, Luttrell, Yahr (b0240) 1994
Travis, Ekici, Freels (b0260) 2013
Cui, Tang, Guo, Yuan, Yan (b0030) 2008; 238
Ho, Hong, Mack (b0085) 2004
Scavuzzo (b0195) 1965; 21
Johansson (b0095) 1959
Renfro, Chandler, Cook, Freels, Griffin, Ilas, Primm, Sease (b0175) 2011
Kuzmin, Mierka, Turek (b0135) 2007; 1
Michelin, Llewellyn Smith (b0150) 2009; 25
Travis (b0255) 2014
Swinson, Battiste, Luttrell, Yahr (b0225) 1992; 5
Khane, Jain, Freels (b0125) 2012
Swinson, Battiste, Luttrell, Yahr (b0235) 1993
Titow (b0250) 1984
Sartory (b0185) 1991
Stromquist, Sisman (b0220) 1948
Burkes, Mickum, Wachs (b0010) 2010
Miller (b0155) 1960
Sartory (b0190) 1993
Kerboua, Lakis, Thomas, Marcouiller (b0115) 2008; 2
Siman-Tov, Gambill, Nelson, Ruggles, Yoder (b0200) 1991
GTRI Website, 2014. Global Threat Reduction Initiative, National Nuclear Security Administration. URL
Wick (b0285) 1969; 23
Kennedy, Jesse, Slater, Solbrekken (b0110) 2012
Jain, Freels, Cook (b0090) 2012
Kennedy (b0105) 2015
Johansson (10.1016/j.anucene.2019.02.001_b0095) 1959
(10.1016/j.anucene.2019.02.001_b0165) 2013
Yoder (10.1016/j.anucene.2019.02.001_b0290) 1994
Heil (10.1016/j.anucene.2019.02.001_b0075) 2008; 43
Khane (10.1016/j.anucene.2019.02.001_b0120) 2012
Michelin (10.1016/j.anucene.2019.02.001_b0150) 2009; 25
Freels (10.1016/j.anucene.2019.02.001_b0055) 2010
Kennedy (10.1016/j.anucene.2019.02.001_b0105) 2015
Cui (10.1016/j.anucene.2019.02.001_b0030) 2008; 238
Burkes (10.1016/j.anucene.2019.02.001_b0010) 2010
Cekirge (10.1016/j.anucene.2019.02.001_b0015) 1978; 4
Siman-Tov (10.1016/j.anucene.2019.02.001_b0200) 1991
10.1016/j.anucene.2019.02.001_b0025
Renfro (10.1016/j.anucene.2019.02.001_b0175) 2011
10.1016/j.anucene.2019.02.001_b0065
McLain (10.1016/j.anucene.2019.02.001_b0145) 1967
Wick (10.1016/j.anucene.2019.02.001_b0280) 1969; 23
Morris (10.1016/j.anucene.2019.02.001_b0160) 1993
Swinson (10.1016/j.anucene.2019.02.001_b0235) 1993
Guo (10.1016/j.anucene.2019.02.001_b0070) 2000; 122
Swinson (10.1016/j.anucene.2019.02.001_b0240) 1994
Tschaepe (10.1016/j.anucene.2019.02.001_b0265) 2008
Scavuzzo (10.1016/j.anucene.2019.02.001_b0195) 1965; 21
Wang (10.1016/j.anucene.2019.02.001_b0275) 2013
Smissaert (10.1016/j.anucene.2019.02.001_b0210) 1968; 7
Kane (10.1016/j.anucene.2019.02.001_b0100) 1962; 15
Jain (10.1016/j.anucene.2019.02.001_b0090) 2012
Travis (10.1016/j.anucene.2019.02.001_b0255) 2014
Groninger (10.1016/j.anucene.2019.02.001_b0060) 1963; 16
Travis (10.1016/j.anucene.2019.02.001_b0260) 2013
Curtis (10.1016/j.anucene.2019.02.001_b0035) 2013
Miller (10.1016/j.anucene.2019.02.001_b0155) 1960
Khane (10.1016/j.anucene.2019.02.001_b0125) 2012
Swinson (10.1016/j.anucene.2019.02.001_b0245) 1995; 35
Kennedy (10.1016/j.anucene.2019.02.001_b0110) 2012
Wambsganss (10.1016/j.anucene.2019.02.001_b0270) 1967; 5
Freels (10.1016/j.anucene.2019.02.001_b0050) 2011
Pavone (10.1016/j.anucene.2019.02.001_b0170) 1983; 74
Smissaert (10.1016/j.anucene.2019.02.001_b0215) 1969; 9
10.1016/j.anucene.2019.02.001_b0005
Siman-Tov (10.1016/j.anucene.2019.02.001_b0205) 1997
Wick (10.1016/j.anucene.2019.02.001_b0285) 1969; 23
Kerboua (10.1016/j.anucene.2019.02.001_b0115) 2008; 2
Swinson (10.1016/j.anucene.2019.02.001_b0225) 1992; 5
Sartory (10.1016/j.anucene.2019.02.001_b0190) 1993
Roth (10.1016/j.anucene.2019.02.001_b0180) 2012
10.1016/j.anucene.2019.02.001_b0080
Swinson (10.1016/j.anucene.2019.02.001_b0230) 1993
Kuzmin (10.1016/j.anucene.2019.02.001_b0135) 2007; 1
Luttrell (10.1016/j.anucene.2019.02.001_b0140) 1995
Curtis (10.1016/j.anucene.2019.02.001_b0040) 2017; 10
Stromquist (10.1016/j.anucene.2019.02.001_b0220) 1948
Sartory (10.1016/j.anucene.2019.02.001_b0185) 1991
Kim (10.1016/j.anucene.2019.02.001_b0130) 1977; 44
Titow (10.1016/j.anucene.2019.02.001_b0250) 1984
Felde (10.1016/j.anucene.2019.02.001_b0045) 1992
Chandler (10.1016/j.anucene.2019.02.001_b0020) 2011
Ho (10.1016/j.anucene.2019.02.001_b0085) 2004
References_xml – volume: 16
  start-page: 218
  year: 1963
  end-page: 226
  ident: b0060
  article-title: Flow induced deflections of parallel flat plates
  publication-title: Nucl. Sci. Eng.
  contributor:
    fullname: Kane
– year: 2015
  ident: b0105
  article-title: Development and Experimental Benchmarking of Numeric Fluid Structure Interaction Models for Research Reactor Fuel Analysis
  contributor:
    fullname: Kennedy
– year: 2013
  ident: b0035
  article-title: Fluid-structure interaction modeling of high-aspect ratio nuclear fuel plates using COMSOL
  publication-title: 2013 COMSOL Conference
  contributor:
    fullname: Freels
– volume: 238
  start-page: 1629
  year: 2008
  end-page: 1635
  ident: b0030
  article-title: Flow-induced vibration and stability of an element model for parallel-plate fuel assemblies
  publication-title: Nucl. Eng. Des.
  contributor:
    fullname: Yan
– year: 2013
  ident: b0165
  article-title: ORNL TM, High Flux Isotope Reactor Safety Analysis Report
  publication-title: Oak Ridge National Laboratory
– year: 1993
  ident: b0190
  article-title: Nonlinear Analysis of Hydraulic Buckling Instability of ANS Involute Fuel Plates
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Sartory
– year: 1959
  ident: b0095
  article-title: Hydraulic Instability of Reactor Parallel-Plate Fuel Assemblies
  publication-title: General Electric Company
  contributor:
    fullname: Johansson
– year: 2012
  ident: b0090
  article-title: 3D COMSOL Simulations for Thermal Deflection of HFIR Fuel Plate in the Cheverton-Kelley Experiments
  contributor:
    fullname: Cook
– volume: 1
  start-page: 193
  year: 2007
  end-page: 206
  ident: b0135
  article-title: On the implementation of the
  publication-title: Int. J. Comput. Sci. Math.
  contributor:
    fullname: Turek
– year: 2013
  ident: b0275
  article-title: Model application of COMSOL pipe flow module to develop a high flux isotope reactor system loop
  publication-title: 2013 COMSOL Conference
  contributor:
    fullname: Freels
– year: 2011
  ident: b0175
  article-title: Low-Enriched Uranium Fuel Conversion Activities for the High Flux Isotope Reactor, Annual Report for FY 2011
  contributor:
    fullname: Sease
– year: 1994
  ident: b0290
  article-title: Steady-State Thermal-Hydraulic Design and Analysis of the Advanced Neutron Source Reactor
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Stovall
– volume: 10
  year: 2017
  ident: b0040
  article-title: Predicting large deflections of multiplate fuel elements using a monolithic FSI approach
  publication-title: Nucl. Sci. Eng.
  contributor:
    fullname: Ekici
– volume: 5
  start-page: 268
  year: 1967
  end-page: 276
  ident: b0270
  article-title: Second order effects as related to critical coolant flow velocities and reactor parallel plate fuel assemblies
  publication-title: Nucl. Eng. Des.
  contributor:
    fullname: Wambsganss
– volume: 7
  start-page: 535
  year: 1968
  end-page: 546
  ident: b0210
  article-title: Static and dynamic hydroelastic instabilities in MTR-type fuel elements part 1. Introduction and experimental investigation
  publication-title: Nucl. Eng. Des.
  contributor:
    fullname: Smissaert
– year: 1993
  ident: b0230
  article-title: Fuel Plate Stability Experiments and Analysis for the Advanced Neutron Source
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Yahr
– volume: 21
  start-page: 463
  year: 1965
  end-page: 472
  ident: b0195
  article-title: Hydraulic instability of flat parallel-plate assemblies
  publication-title: Nucl. Sci. Eng.
  contributor:
    fullname: Scavuzzo
– volume: 23
  start-page: 407
  year: 1969
  end-page: 418
  ident: b0285
  article-title: Hydro-elastic behavior of multiple-plate fuel-assemblies – II: hydro-static divergence
  publication-title: J. Nucl. Energy
  contributor:
    fullname: Wick
– year: 2011
  ident: b0020
  article-title: Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor
  contributor:
    fullname: Chandler
– year: 1997
  ident: b0205
  article-title: Progress Report on the ANS Thermal-Hydraulic Test Loop Operation and Results
  contributor:
    fullname: Yoder
– volume: 74
  start-page: 79
  year: 1983
  end-page: 89
  ident: b0170
  article-title: Laminar flow induced deflections of stacked plates
  publication-title: Nucl. Eng. Des.
  contributor:
    fullname: Scarton
– year: 2011
  ident: b0050
  article-title: Multiphysics simulations of the complex 3D geometry of the high flux isotope reactor fuel elements using COMSOL
  publication-title: 2011 COMSOL Conference
  contributor:
    fullname: Jain
– year: 2014
  ident: b0255
  article-title: Simulating High Flux Isotope Reactor Core Thermal-Hydraulics via Interdimensional Model Coupling
  contributor:
    fullname: Travis
– volume: 9
  start-page: 105
  year: 1969
  end-page: 122
  ident: b0215
  article-title: Static and dynamic hydroelastic instabilities in MTR-type fuel elements part 2. Theoretical investigation and discussion
  publication-title: Nucl. Eng. Des.
  contributor:
    fullname: Smissaert
– volume: 25
  start-page: 1136
  year: 2009
  end-page: 1157
  ident: b0150
  article-title: Linear stability analysis of coupled parallel flexible plates in an axial flow
  publication-title: J. Fluids Struct.
  contributor:
    fullname: Llewellyn Smith
– year: 1960
  ident: b0155
  article-title: Critical Flow Velocities for Collapse of Reactor Parallel-Plate Fuel Assemblies
  publication-title: Knolls Atomic Power Lab
  contributor:
    fullname: Miller
– year: 2008
  ident: b0265
  article-title: Evaluation of HFIR LEU Fuel Using the COMSOL Multiphysics Platform
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Primm III
– year: 2012
  ident: b0180
  article-title: CFD Analysis of Pressure Differentials in a Plate-Type Fuel Assembly
  contributor:
    fullname: Roth
– year: 2004
  ident: b0085
  article-title: Experimental investigation of flow-induced vibration in a parallel plate reactor fuel assembly
  publication-title: 15th Australasian Fluid Mechanics Conference
  contributor:
    fullname: Mack
– volume: 23
  start-page: 387
  year: 1969
  end-page: 405
  ident: b0280
  article-title: Hydro-elastic behavior of multiple-plate fuel-assemblies – I: pressure wave propagation
  publication-title: J. Nucl. Energy
  contributor:
    fullname: Wick
– year: 2013
  ident: b0260
  article-title: Simulating HFIR core thermal hydraulics using 3D-2D model coupling
  publication-title: 2013 COMSOL Conference
  contributor:
    fullname: Freels
– year: 2012
  ident: b0125
  article-title: Development of CFD Models to Support LEU Conversion of ORNL’s High Flux Isotope Reactor
  publication-title: ANS Winter Meeting
  contributor:
    fullname: Freels
– volume: 44
  start-page: 207
  year: 1977
  end-page: 212
  ident: b0130
  article-title: Flow induced bending of rectangular plates
  publication-title: J. Appl. Mech.
  contributor:
    fullname: Scarton
– year: 2012
  ident: b0120
  article-title: COMSOL simulations for steady state thermal hydraulics analyses of ORNL’s high flux isotope reactor
  publication-title: 2012 COMSOL Conference
  contributor:
    fullname: Freels
– year: 1991
  ident: b0200
  article-title: Thermal hydraulic correlations for the advanced neutron source reactor fuel element design and analysis
  publication-title: Proceeding 1991 ASME Winter Annual Meeting, Atlanta
  contributor:
    fullname: Yoder
– volume: 5
  start-page: 133
  year: 1992
  end-page: 143
  ident: b0225
  article-title: Fuel-plate stability experiments and analysis for the advanced neutron source
  publication-title: Symp. Flow-Induced Vib. Noise
  contributor:
    fullname: Yahr
– year: 1984
  ident: b0250
  article-title: PVC Technology
  contributor:
    fullname: Titow
– year: 1995
  ident: b0140
  article-title: Finite Element Analysis of Advanced Neutron Source Fuel Plates
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Luttrell
– year: 2010
  ident: b0055
  article-title: Two-Dimensional Thermal Hydraulic Analysis and Benchmark in Support of HFIR LEU Conversion using COMSOL
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Lowe
– year: 1948
  ident: b0220
  article-title: High Flux Reactor Fuel Assemblies Vibration and Water Flow
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Sisman
– volume: 4
  start-page: 153
  year: 1978
  end-page: 156
  ident: b0015
  article-title: Critical coolant flow velocities in reactors having parallel fuel plates
  publication-title: Comput. Math. Appl.
  contributor:
    fullname: Ural
– volume: 122
  start-page: 502
  year: 2000
  end-page: 508
  ident: b0070
  article-title: Analysis of hydroelastic instabilities of rectangular parallel-plate assemblies
  publication-title: J. Pressure Vessel Technol.
  contributor:
    fullname: Païdoussis
– volume: 43
  start-page: 91
  year: 2008
  end-page: 101
  ident: b0075
  article-title: Solvers for large-displacement fluid-structure interaction problems: segregated versus monolithic approaches
  publication-title: Comput. Mech.
  contributor:
    fullname: Boyle
– volume: 2
  start-page: 525
  year: 2008
  end-page: 539
  ident: b0115
  article-title: Modelling of plates subjected to flowing fluid under various boundary conditions
  publication-title: Eng. Appl. Comput. Fluid Mech.
  contributor:
    fullname: Marcouiller
– year: 1993
  ident: b0235
  article-title: Follow-up Fuel Plate Stability Experiments and Analysis for the Advanced Neutron Source
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Yahr
– year: 2010
  ident: b0010
  article-title: Thermophysical Properties of U-10Mo Alloy
  contributor:
    fullname: Wachs
– year: 1994
  ident: b0240
  article-title: An Examination of the Elastic Structural Response of the Advanced Neutron Source Fuel Plates
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Yahr
– volume: 15
  start-page: 305
  year: 1962
  end-page: 308
  ident: b0100
  article-title: The effect of inlet spacing deviations on the flow-induced deflections of flat plates
  publication-title: Nucl. Sci. Eng.
  contributor:
    fullname: Kane
– year: 1967
  ident: b0145
  article-title: HFIR Fuel Element Steady State Heat Transfer Analysis: Revised Version
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: McLain
– year: 1992
  ident: b0045
  article-title: The advanced neutron source thermal hydraulic test loop
  publication-title: Proceedings 8th Power Plant Dynamics, Control and Testing Symposium, Knoxville, TN
  contributor:
    fullname: Felde
– volume: 35
  start-page: 212
  year: 1995
  end-page: 215
  ident: b0245
  article-title: An experimental investigation of the structural response of reactor fuel plates
  publication-title: Exp. Mech.
  contributor:
    fullname: Yahr
– year: 1993
  ident: b0160
  article-title: High Flux Isotope Reactor System RELAP5 Input Model
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Wendel
– year: 2012
  ident: b0110
  article-title: Fluid-Structure Interaction Modeling and Experimental Benchmarking
  contributor:
    fullname: Solbrekken
– year: 1991
  ident: b0185
  article-title: Analysis of Hydraulic Instabilities of ANS Involute Fuel Plates
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Sartory
– year: 2010
  ident: 10.1016/j.anucene.2019.02.001_b0055
  article-title: Two-Dimensional Thermal Hydraulic Analysis and Benchmark in Support of HFIR LEU Conversion using COMSOL
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Freels
– year: 1959
  ident: 10.1016/j.anucene.2019.02.001_b0095
  article-title: Hydraulic Instability of Reactor Parallel-Plate Fuel Assemblies
  publication-title: General Electric Company
  contributor:
    fullname: Johansson
– volume: 44
  start-page: 207
  year: 1977
  ident: 10.1016/j.anucene.2019.02.001_b0130
  article-title: Flow induced bending of rectangular plates
  publication-title: J. Appl. Mech.
  doi: 10.1115/1.3424025
  contributor:
    fullname: Kim
– year: 1993
  ident: 10.1016/j.anucene.2019.02.001_b0235
  article-title: Follow-up Fuel Plate Stability Experiments and Analysis for the Advanced Neutron Source
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Swinson
– ident: 10.1016/j.anucene.2019.02.001_b0065
– volume: 122
  start-page: 502
  issue: 4
  year: 2000
  ident: 10.1016/j.anucene.2019.02.001_b0070
  article-title: Analysis of hydroelastic instabilities of rectangular parallel-plate assemblies
  publication-title: J. Pressure Vessel Technol.
  doi: 10.1115/1.1286019
  contributor:
    fullname: Guo
– year: 1993
  ident: 10.1016/j.anucene.2019.02.001_b0190
  article-title: Nonlinear Analysis of Hydraulic Buckling Instability of ANS Involute Fuel Plates
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Sartory
– year: 1984
  ident: 10.1016/j.anucene.2019.02.001_b0250
  contributor:
    fullname: Titow
– year: 2010
  ident: 10.1016/j.anucene.2019.02.001_b0010
  contributor:
    fullname: Burkes
– year: 2015
  ident: 10.1016/j.anucene.2019.02.001_b0105
  contributor:
    fullname: Kennedy
– volume: 10
  year: 2017
  ident: 10.1016/j.anucene.2019.02.001_b0040
  article-title: Predicting large deflections of multiplate fuel elements using a monolithic FSI approach
  publication-title: Nucl. Sci. Eng.
  contributor:
    fullname: Curtis
– year: 2012
  ident: 10.1016/j.anucene.2019.02.001_b0125
  article-title: Development of CFD Models to Support LEU Conversion of ORNL’s High Flux Isotope Reactor
  publication-title: ANS Winter Meeting
  contributor:
    fullname: Khane
– year: 2011
  ident: 10.1016/j.anucene.2019.02.001_b0020
  contributor:
    fullname: Chandler
– year: 2012
  ident: 10.1016/j.anucene.2019.02.001_b0090
  contributor:
    fullname: Jain
– ident: 10.1016/j.anucene.2019.02.001_b0005
– volume: 16
  start-page: 218
  year: 1963
  ident: 10.1016/j.anucene.2019.02.001_b0060
  article-title: Flow induced deflections of parallel flat plates
  publication-title: Nucl. Sci. Eng.
  doi: 10.13182/NSE63-A26503
  contributor:
    fullname: Groninger
– year: 1995
  ident: 10.1016/j.anucene.2019.02.001_b0140
  article-title: Finite Element Analysis of Advanced Neutron Source Fuel Plates
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Luttrell
– volume: 21
  start-page: 463
  year: 1965
  ident: 10.1016/j.anucene.2019.02.001_b0195
  article-title: Hydraulic instability of flat parallel-plate assemblies
  publication-title: Nucl. Sci. Eng.
  doi: 10.13182/NSE65-A18790
  contributor:
    fullname: Scavuzzo
– ident: 10.1016/j.anucene.2019.02.001_b0080
– year: 2012
  ident: 10.1016/j.anucene.2019.02.001_b0110
  contributor:
    fullname: Kennedy
– volume: 15
  start-page: 305
  year: 1962
  ident: 10.1016/j.anucene.2019.02.001_b0100
  article-title: The effect of inlet spacing deviations on the flow-induced deflections of flat plates
  publication-title: Nucl. Sci. Eng.
  doi: 10.13182/NSE63-A26441
  contributor:
    fullname: Kane
– volume: 9
  start-page: 105
  year: 1969
  ident: 10.1016/j.anucene.2019.02.001_b0215
  article-title: Static and dynamic hydroelastic instabilities in MTR-type fuel elements part 2. Theoretical investigation and discussion
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/0029-5493(69)90052-1
  contributor:
    fullname: Smissaert
– volume: 74
  start-page: 79
  issue: 1
  year: 1983
  ident: 10.1016/j.anucene.2019.02.001_b0170
  article-title: Laminar flow induced deflections of stacked plates
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/0029-5493(83)90141-3
  contributor:
    fullname: Pavone
– year: 2008
  ident: 10.1016/j.anucene.2019.02.001_b0265
  article-title: Evaluation of HFIR LEU Fuel Using the COMSOL Multiphysics Platform
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Tschaepe
– volume: 43
  start-page: 91
  issue: 1
  year: 2008
  ident: 10.1016/j.anucene.2019.02.001_b0075
  article-title: Solvers for large-displacement fluid-structure interaction problems: segregated versus monolithic approaches
  publication-title: Comput. Mech.
  doi: 10.1007/s00466-008-0270-6
  contributor:
    fullname: Heil
– year: 2012
  ident: 10.1016/j.anucene.2019.02.001_b0180
  contributor:
    fullname: Roth
– volume: 7
  start-page: 535
  year: 1968
  ident: 10.1016/j.anucene.2019.02.001_b0210
  article-title: Static and dynamic hydroelastic instabilities in MTR-type fuel elements part 1. Introduction and experimental investigation
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/0029-5493(68)90103-9
  contributor:
    fullname: Smissaert
– year: 1991
  ident: 10.1016/j.anucene.2019.02.001_b0200
  article-title: Thermal hydraulic correlations for the advanced neutron source reactor fuel element design and analysis
  contributor:
    fullname: Siman-Tov
– year: 2014
  ident: 10.1016/j.anucene.2019.02.001_b0255
  contributor:
    fullname: Travis
– volume: 4
  start-page: 153
  year: 1978
  ident: 10.1016/j.anucene.2019.02.001_b0015
  article-title: Critical coolant flow velocities in reactors having parallel fuel plates
  publication-title: Comput. Math. Appl.
  doi: 10.1016/0898-1221(78)90025-1
  contributor:
    fullname: Cekirge
– year: 2004
  ident: 10.1016/j.anucene.2019.02.001_b0085
  article-title: Experimental investigation of flow-induced vibration in a parallel plate reactor fuel assembly
  contributor:
    fullname: Ho
– year: 1993
  ident: 10.1016/j.anucene.2019.02.001_b0160
  article-title: High Flux Isotope Reactor System RELAP5 Input Model
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Morris
– year: 2013
  ident: 10.1016/j.anucene.2019.02.001_b0165
  article-title: ORNL TM, High Flux Isotope Reactor Safety Analysis Report
  publication-title: Oak Ridge National Laboratory
– year: 2012
  ident: 10.1016/j.anucene.2019.02.001_b0120
  article-title: COMSOL simulations for steady state thermal hydraulics analyses of ORNL’s high flux isotope reactor
  contributor:
    fullname: Khane
– year: 2011
  ident: 10.1016/j.anucene.2019.02.001_b0050
  article-title: Multiphysics simulations of the complex 3D geometry of the high flux isotope reactor fuel elements using COMSOL
  contributor:
    fullname: Freels
– year: 2013
  ident: 10.1016/j.anucene.2019.02.001_b0275
  article-title: Model application of COMSOL pipe flow module to develop a high flux isotope reactor system loop
  contributor:
    fullname: Wang
– ident: 10.1016/j.anucene.2019.02.001_b0025
– year: 1967
  ident: 10.1016/j.anucene.2019.02.001_b0145
  article-title: HFIR Fuel Element Steady State Heat Transfer Analysis: Revised Version
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: McLain
– year: 1993
  ident: 10.1016/j.anucene.2019.02.001_b0230
  article-title: Fuel Plate Stability Experiments and Analysis for the Advanced Neutron Source
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Swinson
– volume: 23
  start-page: 387
  year: 1969
  ident: 10.1016/j.anucene.2019.02.001_b0280
  article-title: Hydro-elastic behavior of multiple-plate fuel-assemblies – I: pressure wave propagation
  publication-title: J. Nucl. Energy
  doi: 10.1016/0022-3107(69)90047-1
  contributor:
    fullname: Wick
– year: 2013
  ident: 10.1016/j.anucene.2019.02.001_b0260
  article-title: Simulating HFIR core thermal hydraulics using 3D-2D model coupling
  contributor:
    fullname: Travis
– year: 1994
  ident: 10.1016/j.anucene.2019.02.001_b0240
  article-title: An Examination of the Elastic Structural Response of the Advanced Neutron Source Fuel Plates
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Swinson
– volume: 5
  start-page: 133
  year: 1992
  ident: 10.1016/j.anucene.2019.02.001_b0225
  article-title: Fuel-plate stability experiments and analysis for the advanced neutron source
  publication-title: Symp. Flow-Induced Vib. Noise
  contributor:
    fullname: Swinson
– year: 1991
  ident: 10.1016/j.anucene.2019.02.001_b0185
  article-title: Analysis of Hydraulic Instabilities of ANS Involute Fuel Plates
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Sartory
– year: 1948
  ident: 10.1016/j.anucene.2019.02.001_b0220
  article-title: High Flux Reactor Fuel Assemblies Vibration and Water Flow
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Stromquist
– volume: 1
  start-page: 193
  issue: 2
  year: 2007
  ident: 10.1016/j.anucene.2019.02.001_b0135
  article-title: On the implementation of the κ-ε turbulence model in incompressible flow solvers based on a finite element discretisation
  publication-title: Int. J. Comput. Sci. Math.
  doi: 10.1504/IJCSM.2007.016531
  contributor:
    fullname: Kuzmin
– year: 2011
  ident: 10.1016/j.anucene.2019.02.001_b0175
  contributor:
    fullname: Renfro
– volume: 5
  start-page: 268
  year: 1967
  ident: 10.1016/j.anucene.2019.02.001_b0270
  article-title: Second order effects as related to critical coolant flow velocities and reactor parallel plate fuel assemblies
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/0029-5493(67)90064-7
  contributor:
    fullname: Wambsganss
– year: 2013
  ident: 10.1016/j.anucene.2019.02.001_b0035
  article-title: Fluid-structure interaction modeling of high-aspect ratio nuclear fuel plates using COMSOL
  contributor:
    fullname: Curtis
– year: 1994
  ident: 10.1016/j.anucene.2019.02.001_b0290
  article-title: Steady-State Thermal-Hydraulic Design and Analysis of the Advanced Neutron Source Reactor
  publication-title: Oak Ridge National Laboratory
  contributor:
    fullname: Yoder
– volume: 238
  start-page: 1629
  year: 2008
  ident: 10.1016/j.anucene.2019.02.001_b0030
  article-title: Flow-induced vibration and stability of an element model for parallel-plate fuel assemblies
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/j.nucengdes.2008.01.010
  contributor:
    fullname: Cui
– volume: 2
  start-page: 525
  year: 2008
  ident: 10.1016/j.anucene.2019.02.001_b0115
  article-title: Modelling of plates subjected to flowing fluid under various boundary conditions
  publication-title: Eng. Appl. Comput. Fluid Mech.
  contributor:
    fullname: Kerboua
– year: 1992
  ident: 10.1016/j.anucene.2019.02.001_b0045
  article-title: The advanced neutron source thermal hydraulic test loop
  contributor:
    fullname: Felde
– year: 1997
  ident: 10.1016/j.anucene.2019.02.001_b0205
  contributor:
    fullname: Siman-Tov
– volume: 23
  start-page: 407
  issue: 7
  year: 1969
  ident: 10.1016/j.anucene.2019.02.001_b0285
  article-title: Hydro-elastic behavior of multiple-plate fuel-assemblies – II: hydro-static divergence
  publication-title: J. Nucl. Energy
  doi: 10.1016/0022-3107(69)90048-3
  contributor:
    fullname: Wick
– year: 1960
  ident: 10.1016/j.anucene.2019.02.001_b0155
  article-title: Critical Flow Velocities for Collapse of Reactor Parallel-Plate Fuel Assemblies
  publication-title: Knolls Atomic Power Lab
  contributor:
    fullname: Miller
– volume: 25
  start-page: 1136
  year: 2009
  ident: 10.1016/j.anucene.2019.02.001_b0150
  article-title: Linear stability analysis of coupled parallel flexible plates in an axial flow
  publication-title: J. Fluids Struct.
  doi: 10.1016/j.jfluidstructs.2009.06.002
  contributor:
    fullname: Michelin
– volume: 35
  start-page: 212
  issue: 3
  year: 1995
  ident: 10.1016/j.anucene.2019.02.001_b0245
  article-title: An experimental investigation of the structural response of reactor fuel plates
  publication-title: Exp. Mech.
  doi: 10.1007/BF02319660
  contributor:
    fullname: Swinson
SSID ssj0012844
Score 2.255062
Snippet This paper describes the modeling and simulation of fluid structure interactions (FSI) of involute-shaped fuel plates used in nuclear research reactors. We...
SourceID osti
crossref
elsevier
SourceType Open Access Repository
Aggregation Database
Publisher
StartPage 184
SubjectTerms ENGINEERING
Fluid-Structure Interaction
High flux isotope reactor
High FluxIsotope Reactor
Involute Fuel Plates
Thermal-hydraulics
Title Deflection predictions of involute-shaped fuel plates using a fully-coupled numerical approach
URI https://dx.doi.org/10.1016/j.anucene.2019.02.001
https://www.osti.gov/biblio/1502600
Volume 130
hasFullText 1
inHoldings 1
isFullTextHit
isPrint
link http://sdu.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwtV3fT9swELa6IqTxgIBtGj82-WFvlVkcByd5RDSD7YEXmMTTIsexNViVVm3zwH_PXZw4gW0am7SXqHIVN_V9Od-dv7sj5EMoSxuHImVSFgmLpAiYKoqCKSvTSJVpIBuC7MVVfHmTTLMoG406Sfdj_1XSMAayxszZv5C2nxQG4DPIHK4gdbg-S-5TY2fG9f9eLPEUxlPdbitURWvDVt_VAuxMW5sZdpHGyGvdhAzUBKPx90zP68Ws4QW485yZLz0-tGX72ssVFkVWy4lpEgn9sUaNnZ476xg7w0_Ojz1elgZ2Zc_TnUz9N9mPW-0oBnhIpYdhCcyESoZhCZ8v05OTmhytQGKVdackjVO5SSwYOJ7BI53cHtY4rcpdF7l2g-auvddPut-FIe4wZVvD_0XaXurqsfJ-s_MUxCt8FnwUsGCx5hFs4xshKCvQlRunn7ObL_4sCjZwV4SsffY-D-zjL3_sdxbOeA5Ke2C8XO-Q7dbroKcOLrtkZKo9sjWoRblHNhsusF69It96CNEBhOjc0icQoggh6iBEGwhRRR9BiHoI0Q5Cr8nXT9n12QVr23AwLRKxZjxUpowKXqSaayFKq4IiLFOtucG3WRkRWBlyc5JKZH2GymrwOWJwDRIB3m0k3pBxNa_MW0KTEwxXyCCKYgueQgHzxJE1lnPNhZblPjnuli5fuGoreUdDvMvbtc5xrfMgRDrmPkm6Bc5bk9GZgjmg4k-3HqJA8DYsl6yRVwb3gYOEPRsO_n3iQ_KyfyGOyHi9rM078mJV1u9baD0Am6WcFg
link.rule.ids 230,315,782,786,887,27933,27934
linkProvider Elsevier
openUrl ctx_ver=Z39.88-2004&ctx_enc=info%3Aofi%2Fenc%3AUTF-8&rfr_id=info%3Asid%2Fsummon.serialssolutions.com&rft_val_fmt=info%3Aofi%2Ffmt%3Akev%3Amtx%3Ajournal&rft.genre=article&rft.atitle=Deflection+predictions+of+involute-shaped+fuel+plates+using+a+fully-coupled+numerical+approach&rft.jtitle=Annals+of+nuclear+energy&rft.au=Curtis%2C+Franklin+G.&rft.au=Freels%2C+James+D.&rft.au=Ekici%2C+Kivanc&rft.date=2019-08-01&rft.pub=Elsevier+Ltd&rft.issn=0306-4549&rft.eissn=1873-2100&rft.volume=130&rft.spage=184&rft.epage=191&rft_id=info:doi/10.1016%2Fj.anucene.2019.02.001&rft.externalDocID=S0306454919300702
thumbnail_l http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/lc.gif&issn=0306-4549&client=summon
thumbnail_m http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/mc.gif&issn=0306-4549&client=summon
thumbnail_s http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/sc.gif&issn=0306-4549&client=summon