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For: Liu K, Wang M, Gan F, Tian W, Qiu S, Su G. Numerical investigation of flow and heat transfer characteristics in plate-type fuel channels of IAEA MTR based on OpenFOAM. Progress in Nuclear Energy 2021;141:103963. [DOI: 10.1016/j.pnucene.2021.103963] [Citation(s) in RCA: 9] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
Number Cited by Other Article(s)
1
Effects of surface alteration on CHF related to IVR accident scenarios: A review. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104653] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 03/16/2023]
2
Li X, Sun W, Ding S, Huang T, Ma Z, Zhang L, Zhu L, Pan LM. Analysis of RELAP5 prediction of countercurrent flow limitation in downcomer at upper plenum test facility. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104608] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/23/2023]
3
Modeling of turbulent diffusion terms for one-dimensional interfacial area transport equation in vertical round channels. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104568] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 01/13/2023]
4
Transient multiphysics characteristics of a space thermionic reactor based on a coupling analysis. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2022.112064] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/12/2022]
5
Gong HJ, Zhang X, Gui N, Huang Y, Yang X. Study of density wave instability in natural circulation with parallel channels under inclined and heaving conditions. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2022.104525] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/12/2022]
6
Qu W, Liu L, Yao W, Xie H, Liu J, Xiong J. Time-resolved PIV measurement of coherent structures downstream of step blockage in a narrow rectangular channel. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109505] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]
7
Liu K, Zhao F, Jin Y, Hu C, Ming Y, Liu Y, Tian R, Liu S. S–CO2 heat transfer characteristics analysis in PCHE and vertical channel. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104472] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
8
Tan B, Yang C, Cai J, Gong Z, Deng R. Experimental and theoretical investigation on the effect of surface porosity on the nucleate flow boiling heat transfer. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104471] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]
9
Li Z, Pan J, Peng H, Chen D, Lu W, Wu H. Numerical study on subcooled flow boiling in narrow rectangular channel based on OpenFOAM. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104451] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/05/2022]
10
Zhang R, Du Z, Ren T, Shi J, Cheng J. Development of flow boiling mechanism model and its application to rectangular narrow channel under atmosphere pressure. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104381] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/15/2022]
11
Hedayat A, Davari A. Feasibility study to increase the reactor power at natural convection mode in Tehran Research Reactor (TRR) through a hybrid thermal-hydraulic simulation and analysis using the RELAP5 code and Computational Fluid Dynamic (CFD) modeling by ANSYS-FLUENT. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104285] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
12
Existing DNB-type CHF mechanistic models and relations with visualized experiments in forced convective flow boiling: A review. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104225] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
13
Liu J, Song P, Zhang D, Wang S, Lin C, Liu Y, Zhou L, Wang C, Tian W, Qiu S, Su G, Tian W. Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.01.026] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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