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Sui D, Yu J, Wang Z, Zhang J, Peng J, Lu D. Sub-channel analysis code development and core thermal calculation for fast reactor refueling cycle. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109215] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Liu JT, Peng TJ, Wang G, Su XK, Tao YJ, Fan DJ, Li XW, He MH, Xu HS, Gu L. Sub-channel analysis of lead–bismuth fast reactor fuel assembly with wire spacers for China initiative accelerator driven system. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108965] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Yang BW, Ninokata H, Long J, Liu A, Han B. Subchannel analysis – Current practice and development for the future. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111477] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Deng J, Lu Q, Wu D, Wang C, Guo C, Mi Z, Huang D, Yan M, Wang X, Chen X, Li P. Sub-channel code development of lead-bismuth eutectic fast reactor available for multiple fuel assembly structures. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107769] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Song M, Jeong JH, Kim ES. Investigation on subchannel flow distribution in wire-wrapped 37 and 61-pin bundle using computational fluid dynamics. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110904] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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6
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Liu A, Yang BW, Han B, Zhu X. Turbulent Mixing Models and Other Mixing Coefficients in Subchannel Codes—A Review Part A: Single Phase. NUCL TECHNOL 2020. [DOI: 10.1080/00295450.2020.1792753] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
Affiliation(s)
- Aiguo Liu
- Delta Energy Group, No. 413, Venture Building, No. 1 Changjiang Road, Economic and Technology Development Zone, Jiaozhou, Qingdao, 266300, Shandong, China
- DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, No. 1 Huiying Road, Economic and Technology Development Zone, Jiaozhou, Qingdao, 266300, Shandong, China
| | - Bao-Wen Yang
- Delta Energy Group, No. 413, Venture Building, No. 1 Changjiang Road, Economic and Technology Development Zone, Jiaozhou, Qingdao, 266300, Shandong, China
- DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, No. 1 Huiying Road, Economic and Technology Development Zone, Jiaozhou, Qingdao, 266300, Shandong, China
| | - Bin Han
- Delta Energy Group, No. 413, Venture Building, No. 1 Changjiang Road, Economic and Technology Development Zone, Jiaozhou, Qingdao, 266300, Shandong, China
- DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer, No. 1 Huiying Road, Economic and Technology Development Zone, Jiaozhou, Qingdao, 266300, Shandong, China
| | - Xianlin Zhu
- Xi’an Jiaotong University, School of Nuclear Science and Technology, Xianning West Road 28, Xi’an, 710049, Shaanxi, China
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Orlova EE, Smirnov VP, Vlasenko AE, Palagin AV. Celsist Subchannel Module Aided Simulation of Liquid-Metal Coolant Flow in Experimental FA. ATOM ENERGY+ 2020. [DOI: 10.1007/s10512-020-00653-z] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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8
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Transient sub-channel code development for lead-cooled fast reactor using the second-order upwind scheme. PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2018.09.022] [Citation(s) in RCA: 10] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Choi SR, Lim JY, Won JH, Kim JH, Cheon JS. Thermo-mechanical behavior of all the metallic fuel rods in a sodium-cooled fast reactor. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.09.006] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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10
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Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.07.006] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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11
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Chen S, Chen Y, Todreas N. The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.05.010] [Citation(s) in RCA: 32] [Impact Index Per Article: 5.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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12
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A review of sub-channel thermal hydraulic codes for nuclear reactor core and future directions. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.03.012] [Citation(s) in RCA: 37] [Impact Index Per Article: 6.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Padmakumar G, Velusamy K, Prasad B, Lijukrishnan P, Pandey G, Selvaraj P. Thermal-hydraulic effects of inserts in a fast reactor fuel bundle. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.03.037] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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14
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Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2017.12.005] [Citation(s) in RCA: 13] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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15
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Moslehi Azad H, Shirani A. Subchannel calculation of sodium two phase flow in a 37-rods bundle in loss of flow experiment with different constitutive correlations. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2017.09.016] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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16
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Jeong JH, Song MS, Lee KL. CFD investigation of three-dimensional flow phenomena in a JAEA 127-pin wire-wrapped fuel assembly. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.08.008] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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17
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Moslehi Azad H, Shirani A. The effect of various pressure drop and flow mixing correlations on subchannel calculation of sodium temperature distribution in a 19 pins wire wrapped bundle. PROGRESS IN NUCLEAR ENERGY 2017. [DOI: 10.1016/j.pnucene.2017.04.022] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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18
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Experimental study of the flow characteristics in an SFR type 61-pin rod bundle using iso-kinetic sampling method. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.03.024] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Jeong HY, Ha KS, Chang WP, Kwon YM, Lee YB. Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code. NUCL TECHNOL 2017. [DOI: 10.13182/nt05-a3580] [Citation(s) in RCA: 15] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Hae-Yong Jeong
- Korea Atomic Energy Research Institute, P.O. Box 105 Yuseong, Daejeon 305-600, Korea
| | - Kwi-Seok Ha
- Korea Atomic Energy Research Institute, P.O. Box 105 Yuseong, Daejeon 305-600, Korea
| | - Won-Pyo Chang
- Korea Atomic Energy Research Institute, P.O. Box 105 Yuseong, Daejeon 305-600, Korea
| | - Young-Min Kwon
- Korea Atomic Energy Research Institute, P.O. Box 105 Yuseong, Daejeon 305-600, Korea
| | - Yong-Bum Lee
- Korea Atomic Energy Research Institute, P.O. Box 105 Yuseong, Daejeon 305-600, Korea
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Fricano JW, Buongiorno J. Development and Application of an Integrated Fuel Performance and Subchannel Model for Analysis of Sodium Fast Reactors. NUCL TECHNOL 2017. [DOI: 10.13182/nt13-a19869] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- J. W. Fricano
- Massachusetts Institute of Technology, 77 Massachusetts Avenue Cambridge, Massachusetts 02141
| | - J. Buongiorno
- Massachusetts Institute of Technology, 77 Massachusetts Avenue Cambridge, Massachusetts 02141
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Jeong JH, Song MS, Lee KL. RANS based CFD methodology for a real scale 217-pin wire-wrapped fuel assembly of KAERI PGSFR. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.01.007] [Citation(s) in RCA: 22] [Impact Index Per Article: 3.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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22
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Hu R, Yu Y. A computationally efficient method for full-core conjugate heat transfer modeling of sodium fast reactors. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.08.018] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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23
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Hartanto D, Kim I, Kim C, Kim Y. An LEU-loaded long-life innovative sodium-cooled fast reactor (iSFR) with novel and passive safety devices. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2016.04.051] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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24
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Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2016.01.034] [Citation(s) in RCA: 23] [Impact Index Per Article: 2.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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25
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Lodi F, Grasso G, Mattioli D, Sumini M. ANTEO+: A subchannel code for thermal-hydraulic analysis of liquid metal cooled systems. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.03.001] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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26
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Pothukuchi H, Patnaik B, Prasad B. Sub-channel analysis of rod bundle thermal hydraulics: Effect of eccentricity and blockage. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.01.034] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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27
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Naveen Raj M, Velusamy K. Characterization of velocity and temperature fields in a 217 pin wire wrapped fuel bundle of sodium cooled fast reactor. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.09.008] [Citation(s) in RCA: 24] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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28
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A porous medium model for predicting the duct wall temperature of sodium fast reactor fuel assembly. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.09.020] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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29
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Jeong JH, Yoo J, Lee KL, Ha KS. Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel bundle for SFR. NUCLEAR ENGINEERING AND TECHNOLOGY 2015. [DOI: 10.1016/j.net.2015.06.001] [Citation(s) in RCA: 20] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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30
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Tak T, Lee D, Kim T, Hong SG. Optimization study of Ultra-long Cycle Fast Reactor core concept. ANN NUCL ENERGY 2014. [DOI: 10.1016/j.anucene.2014.06.030] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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32
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Subchannel analysis of a small ultra-long cycle fast reactor core. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.01.016] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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33
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Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors. PROGRESS IN NUCLEAR ENERGY 2014. [DOI: 10.1016/j.pnucene.2013.11.006] [Citation(s) in RCA: 23] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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34
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Wu Y, Li X, Yu X, Qiu S, Su G, Tian W. Subchannel thermal-hydraulic analysis of the fuel assembly for liquid sodium cooled fast reactor. PROGRESS IN NUCLEAR ENERGY 2013. [DOI: 10.1016/j.pnucene.2013.05.001] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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35
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Pramuditya S, Takahashi M. Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method. ANN NUCL ENERGY 2013. [DOI: 10.1016/j.anucene.2012.11.011] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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36
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RAZA W, KIM KY. Comparative Analysis of Flow and Convective Heat Transfer between 7-Pin and 19-Pin Wire-Wrapped Fuel Assemblies. J NUCL SCI TECHNOL 2012. [DOI: 10.1080/18811248.2008.9711465] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
Affiliation(s)
- Wasim RAZA
- a Department of Mechanical Engineering , Inha University , 253, Yonghyun-Dong, Nam-Gu, Incheon , 402-751 , Rep. of Korea
| | - Kwang-Yong KIM
- a Department of Mechanical Engineering , Inha University , 253, Yonghyun-Dong, Nam-Gu, Incheon , 402-751 , Rep. of Korea
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37
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Memmott M, Buongiorno J, Hejzlar P. On the use of RELAP5-3D as a subchannel analysis code. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2009.11.006] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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38
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Jeong HY, Ha KS, Kwon YM, Lee YB, Hahn D. Analysis of three different types of blockage in a sodium flow path with the MATRA-LMR-FB code. ANN NUCL ENERGY 2009. [DOI: 10.1016/j.anucene.2009.01.010] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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39
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Raza W, Kim KY. Shape Optimization of 19-Pin Wire-Wrapped Fuel Assembly of LMR Using Multiobjective Evolutionary Algorithm. NUCL SCI ENG 2009. [DOI: 10.13182/nse161-245] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Wasim Raza
- Inha University, Department of Mechanical Engineering, Incheon, 402-751, Korea
| | - Kwang-Yong Kim
- Inha University, Department of Mechanical Engineering, Incheon, 402-751, Korea
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40
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Raza W, Kim KY. Effects of wire-spacer shape in LMR on thermal–hydraulic performance. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2008.05.003] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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41
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Raza W, Kim KY. Shape optimization of wire-wrapped fuel assembly using Kriging metamodeling technique. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.10.018] [Citation(s) in RCA: 17] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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42
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Raza W, Kim KY. Multiobjective Optimization of a Wire-Wrapped LMR Fuel Assembly. NUCL TECHNOL 2008. [DOI: 10.13182/nt08-a3932] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Wasim Raza
- Inha University Department of Mechanical Engineering, Incheon 402-751, Republic of Korea
| | - Kwang-Yong Kim
- Inha University Department of Mechanical Engineering, Incheon 402-751, Republic of Korea
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RAZA W, KIM KY. Comparative Analysis of Flow and Convective Heat Transfer between 7-Pin and 19-Pin Wire-Wrapped Fuel Assemblies. J NUCL SCI TECHNOL 2008. [DOI: 10.3327/jnst.45.653] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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44
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Jeong HY, Ha KS, Kwon YM, Lee YB, Hahn D, Cahalan JE, Dunn FE. Evaluation of the conduction shape factor with a CFD code for a liquid–metal heat transfer in heated triangular rod bundles. NUCLEAR ENGINEERING AND DESIGN 2007. [DOI: 10.1016/j.nucengdes.2006.09.030] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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