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For: Xiong J, Cheng X, Yang Y. Numerical analysis on supercritical water heat transfer in a 2 × 2 rod bundle. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.02.005] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
Number Cited by Other Article(s)
1
Kumar G, Singh RK. Supercritical water flow in heated wire wrapped rod bundle channels: A review. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104620] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/23/2023]
2
Zhao M, Gu H. Experimental and numerical investigation on heat transfer of supercritical water flowing upward in 2 × 2 rod bundles. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110903] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
3
Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107450] [Citation(s) in RCA: 16] [Impact Index Per Article: 3.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
4
Feng W, Zhang X, Chen H. Simulation of oxygen mass transfer in fuel assemblies under flowing lead-bismuth eutectic. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2019.10.026] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
5
Brogna C, Pucciarelli A, Ambrosini W, Razumovskiy V, Pis'mennyi E. Capabilities of high y+ wall approaches in predicting heat transfer to supercritical fluids in rod bundle geometries. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.05.053] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
6
Critical heat flux experiments and a post-CHF heat transfer analysis using 2D inverse heat transfer. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.06.011] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
7
Amin MM, Duan Y, He S. Large Eddy Simulation Study on Forced Convection Heat Transfer to Water at Supercritical Pressure in a Trapezoid Annulus. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2017. [DOI: 10.1115/1.4038161] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
8
Bergmann CM, Ormiston SJ, Chatoorgoon V. Comparative study of turbulence model predictions of upward supercritical fluid flow in vertical rod bundle subchannels. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.06.044] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
9
Podila K, Rao Y. CFD modelling of supercritical water flow and heat transfer in a 2 × 2 fuel rod bundle. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.03.019] [Citation(s) in RCA: 21] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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