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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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Validation of the TWOPORFLOW code for the core analysis of liquid metal-cooled reactor with selected experiments. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111708] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Application of an Integral Turbulence Model to Close the Model of an Anisotropic Porous Body as Applied to Rod Structures. FLUIDS 2022. [DOI: 10.3390/fluids7020077] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Abstract
In practice, often devices are ordered rod structures consisting of a large number of rods. Heat exchangers, fuel assemblies of nuclear reactors, and their cores in the case of using caseless assemblies are examples of such devices. Simulation of heat and mass transfer processes in such devices in porous-body approximation can significantly reduce the required resources compared to computational fluid dynamics (CFD) approaches. The paper describes an integral turbulence model developed for defining anisotropic model parameters of a porous body. The parameters of the integral turbulence model were determined by numerical simulations for assemblies of smooth rods, assemblies with spacer grids, and wire-wrapped fuel assemblies. The results of modeling the flow of a liquid metal coolant in an experimental fuel assembly with local blocking of its flow section in anisotropic porous-body approximation using an integral turbulence model are described. The possibility of using the model of an anisotropic porous body with the integral model of turbulence to describe thermal-hydraulic processes during fluid flow in rod structures is confirmed.
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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]
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Acosta F, Rubiolo P, Blanc V, Cadiou T. Application and Benchmarking of a Novel Coupled Methodology for Simulating the Thermomechanical Evolution of Sodium-cooled Fast Reactors Fuel Subassemblies. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2020.111048] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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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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A comparison of three algorithms applied in thermal-hydraulics and neutronics codes coupling for lbe-cooled fast reactor. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107789] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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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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Ali MY, Wu G, Liu S, Jin M, Wang J. Research of coupled wall conduction effects on forced and natural circulation of LBE in CLEAR-S. PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2018.10.009] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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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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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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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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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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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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