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For: Pacio J, Daubner M, Fellmoser F, Litfin K, Wetzel T. Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE. Nuclear Engineering and Design 2018. [DOI: 10.1016/j.nucengdes.2018.01.034] [Citation(s) in RCA: 22] [Impact Index Per Article: 3.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]

For:	Pacio J, Daubner M, Fellmoser F, Litfin K, Wetzel T. Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE. Nuclear Engineering and Design 2018. [DOI: 10.1016/j.nucengdes.2018.01.034] [Citation(s) in RCA: 22] [Impact Index Per Article: 3.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]

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Cited by Other Article(s)

Pacio J, Van Tichelen K, Eckert S, Wondrak T, Di Piazza I, Lorusso P, Tarantino M, Daubner M, Litfin K, Ariyoshi G, Obayashi H, Sasa T. Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.112010] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]

Luo X, Zhang K, Duan W, Chen H. Assessment of different internal flow blockage scenarios for LFR fuel assemblies with different configurations. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109386] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]

The blockage model of Upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111874] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]

Vlasenko AE, Palagin AV. Flow and Heat Transfer Simulation of a Liquid-Metallic Coolant in Experimental FA Using the Sub-Channel Module Celsist. ATOM ENERGY+ 2022. [DOI: 10.1007/s10512-022-00872-6] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]

Kong R, Kim S, Wahlen R, Pike J, Grimm T. Experiments and CFD simulations of the LBE loop in HYST: A new concept for irradiation experiments in a fast-reactor-like environment. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111774] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]

Pacio J, Chen S, Chen Y, Todreas N. Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111606] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]

Flow blockage analysis for fuel assembly in a lead-based fast reactor. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2021.05.007] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]

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]

A collaborative effort towards the accurate prediction of turbulent flow and heat transfer in low-Prandtl number fluids. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110750] [Citation(s) in RCA: 9] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]

Roelofs F. Liquid metal thermal hydraulics: State-of-the-art and future perspectives. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110590] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]

Hassan Y. High-fidelity experimental measurements for modeling and simulation of nuclear engineering applications. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.110181] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]

Roelofs F, Dovizio D, Uitslag-Doolaard H, De Santis D, Mathur A, Mikuz B, Shams A. Core thermal hydraulic CFD support for liquid metal reactors. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.110322] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]

Nguyen T, White L, Vaghetto R, Hassan Y. High-fidelity velocity measurements in a totally blocked interior subchannel of a wire-wrapped 61-pin hexagonal fuel bundle. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.110234] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]

Pacio J, Daubner M, Fellmoser F, Wetzel T. Experimental study of the influence of inter-wrapper flow on liquid-metal cooled fuel assemblies. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.06.007] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]

Van Tichelen K, Kennedy G, Mirelli F, Marino A, Toti A, Rozzia D, Cascioli E, Keijers S, Planquart P. Advanced Liquid-Metal Thermal-Hydraulic Research for MYRRHA. NUCL TECHNOL 2019. [DOI: 10.1080/00295450.2019.1614803] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]