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For: 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] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Number Cited by Other Article(s)
1
Chen J, Zhang D, Song P, Wang X, Wang S, Liang Y, Qiu S, Zhang Y, Wang M, Su G. CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.11.023] [Citation(s) in RCA: 29] [Impact Index Per Article: 4.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
2
Thermal-hydraulic comparisons of 19-pin rod bundles with four circular and trapezoid shaped wire wraps. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.04.017] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
3
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]
4
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]
5
CFD investigation of effect of helical wire-wrap parameters on the thermal hydraulic performance of 217 fuel pin bundle. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2014.10.038] [Citation(s) in RCA: 31] [Impact Index Per Article: 3.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
6
Simultaneous development of flow and temperature fields in wire-wrapped fuel pin bundles of sodium cooled fast reactor. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2013.11.066] [Citation(s) in RCA: 25] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
7
Rolfo S, Péniguel C, Guillaud M, Laurence D. Thermal-hydraulic study of a wire spacer fuel assembly. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2011.11.021] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/14/2022]
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