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For: Jayanti S, Rajesh Reddy K. Effect of spacer grids on CHF in nuclear rod bundles. Nuclear Engineering and Design 2013;261:66-75. [DOI: 10.1016/j.nucengdes.2013.03.044] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
Number Cited by Other Article(s)
1
Cai Q, D'Auria F, Umminger K, Bestion D, Shan J. Prioritizing pressure drop research in nuclear thermal hydraulics. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104358] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/31/2022]
2
Abdollahzadeh Jamalabadi MY, Xi J. Parameter study of the grid spacer position on subcooled boiling in an upward vertical tube at low pressures. JOURNAL OF RADIATION RESEARCH AND APPLIED SCIENCES 2022. [DOI: 10.1016/j.jrras.2022.06.011] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
3
Liu W, Liu Y, Peng S, Jiang G, Liu Y, Li J, Hu Y. Visualization of spacer grid effect on bubble behavior and CHF in a single-rod channel. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111376] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
4
Time averaged tomographic measurements before and after dryout in a simplified BWR subchannel geometry. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111295] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
5
Evaluation of structural effect of BWR spacers on droplet flow dynamics. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111155] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
6
Effect of part-length rods for different BWR subchannel geometries. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110909] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
7
Lyons K, Lee D, Anderson M. Experimental study for critical heat flux in 2x2 rod bundles at high pressure conditions. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110730] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
8
Xiao Y, Li J, Deng J, Gao X, Gu H, Pan J. Study of spacer effects on deteriorated heat transfer of supercritical fluid flow in an annulus. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103306] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
9
Verma SK. Impact of spacer on inter sub-channel mixing of coolant in nuclear fuel bundle: a survey and future patterns of research and advances. KERNTECHNIK 2018. [DOI: 10.3139/124.110951] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
10
CFD analysis of the impact of a novel spacer grid with longitudinal vortex generators on the sub-channel flow and heat transfer of a rod bundle. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.08.029] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
11
Pothukuchi H, Patnaik B, Prasad B. Numerical prediction of dryout in a 19 rod bundle under the effect of eccentricity and blockage. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.10.016] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
12
Agbodemegbe V, Cheng X, Akaho E, Allotey F. An investigation of the effect of split-type mixing vane on extent of crossflow between subchannels through the fuel rod gaps. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.10.036] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
13
Rabiee A, Atf A. 3-D numerical investigation of water/CuO nanofluid critical heat flux phenomenon in a PWR core channel during LOCA. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2015.02.004] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
14
Agbodemegbe V, Cheng X, Akaho E, Allotey F. Correlation for cross-flow resistance coefficient using STAR-CCM+ simulation data for flow of water through rod bundle supported by spacer grid with split-type mixing vane. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.01.003] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
15
CFD Turbulence Study of PWR Spacer-Grids in a Rod Bundle. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2014. [DOI: 10.1155/2014/635651] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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