• Reference Citation Analysis
  • v
  • v
  • Find an Article
Find an Article PDF (4640456)   Today's Articles (156)   Subscriber (50388)
For: Chenu A, Mikityuk K, Chawla R. Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow. Nuclear Engineering and Design 2011. [DOI: 10.1016/j.nucengdes.2011.07.009] [Citation(s) in RCA: 21] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
Number Cited by Other Article(s)
1
Liu M, Wang X, Ni S, Liu L, Gu H. Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109163] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
2
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]
3
Kim H, Chen YM, Hassan Y. Prediction of pressure drop in hexagonal wire-wrapped rod bundles using artificial neural network. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111365] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
4
Data-Driven Reduced-Order Modeling of Convective Heat Transfer in Porous Media. FLUIDS 2021. [DOI: 10.3390/fluids6080266] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
5
Ma Z, Ye T, Ren Q, Pan L, Bu S, Zhang L, Sun W. Friction and local pressure loss characteristics of a 5 × 5 rod bundle with spacer grids. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107106] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
6
Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2019. [DOI: 10.1155/2019/5250894] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
7
Chen S, Chen Y, Todreas N. The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.05.010] [Citation(s) in RCA: 32] [Impact Index Per Article: 5.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
8
Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.05.031] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
9
Bubelis E, Tosello A, Pfrang W, Schikorr M, Mikityuk K, Panadero AL, Martorell S, Ordóñez J, Seubert A, Lerchl G, Stempniewicz M, Alcaro F, De Geus E, Delmaere T, Poumerouly S, Wallenius J. System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.06.015] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
10
Moslehi Azad H, Shirani A. The effect of various pressure drop and flow mixing correlations on subchannel calculation of sodium temperature distribution in a 19 pins wire wrapped bundle. PROGRESS IN NUCLEAR ENERGY 2017. [DOI: 10.1016/j.pnucene.2017.04.022] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
11
Pacio J, Daubner M, Fellmoser F, Litfin K, Marocco L, Stieglitz R, Taufall S, Wetzel T. Heavy-liquid metal heat transfer experiment in a 19-rod bundle with grid spacers. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.02.020] [Citation(s) in RCA: 49] [Impact Index Per Article: 4.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
12
Development of design evaluation tools for the JSFR fuel transfer pot. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.02.021] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
13
Chen S, Todreas N, Nguyen N. Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2013.12.003] [Citation(s) in RCA: 61] [Impact Index Per Article: 6.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
14
Lázaro A, Ammirabile L, Bandini G, Darmet G, Massara S, Dufour P, Tosello A, Gallego E, Jimenez G, Mikityuk K, Schikorr M, Bubelis E, Ponomarev A, Kruessmann R, Stempniewicz M. Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2013.10.019] [Citation(s) in RCA: 16] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
15
Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.06.012] [Citation(s) in RCA: 27] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
16
Hu B, Wu Y, Tian W, Su G, Qiu S. Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor. ANN NUCL ENERGY 2013. [DOI: 10.1016/j.anucene.2012.12.022] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
PrevPage 1 of 1 1Next
© 2004-2024 Baishideng Publishing Group Inc. All rights reserved. 7041 Koll Center Parkway, Suite 160, Pleasanton, CA 94566, USA