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For: Scheuerer M, Heitsch M, Menter F, Egorov Y, Toth I, Bestion D, Pigny S, Paillere H, Martin A, Boucker M, Krepper E, Willemsen S, Muhlbauer P, Andreani M, Smith B, Karlsson R, Henriksson M, Hemstrom B, Karppinen I, Kimber G. Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA). Nuclear Engineering and Design 2005. [DOI: 10.1016/j.nucengdes.2004.08.049] [Citation(s) in RCA: 31] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Number Cited by Other Article(s)
1
Hugo Sanchez-Espinoza V, Zhang K, Campos Muñoz A, Böttcher M. KIT Multi-scale thermal–hydraulic coupling methods for improved simulation of nuclear power plants. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2023.112218] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/27/2023]
2
Investigation on Safety Dynamic Evolution Mechanism of a Distributed Low Carbon Manufacturing System with Large Time Delay. Processes (Basel) 2022. [DOI: 10.3390/pr10091707] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]  Open
3
Wang J, Wang Q, Ding M. Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107165] [Citation(s) in RCA: 18] [Impact Index Per Article: 4.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
4
Liao Y, Krepper E, Lucas D. A baseline closure concept for simulating bubbly flow with phase change: A mechanistic model for interphase heat transfer coefficient. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.04.007] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
5
Jeltsov M, Grishchenko D, Kudinov P. Validation of Star-CCM+ for liquid metal thermal-hydraulics using TALL-3D experiment. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2018.11.015] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
6
Introini C, Lorenzi S, Cammi A, Baroli D, Peters B, Bordas S. A Mass Conservative Kalman Filter Algorithm for Computational Thermo-Fluid Dynamics. MATERIALS (BASEL, SWITZERLAND) 2018;11:E2222. [PMID: 30413109 PMCID: PMC6267179 DOI: 10.3390/ma11112222] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 10/11/2018] [Revised: 10/26/2018] [Accepted: 10/30/2018] [Indexed: 11/16/2022]
7
Eulerian modelling of turbulent bubbly flow based on a baseline closure concept. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.07.021] [Citation(s) in RCA: 33] [Impact Index Per Article: 5.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
8
Henry R, Tiselj I, Snoj L. Transient CFD/Monte-Carlo Neutron Transport Coupling Scheme for simulation of a control rod extraction in TRIGA reactor. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.03.015] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
9
Henry R, Tiselj I, Snoj L. CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.06.018] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
10
Smith BL. On the Establishment of a Web Portal for the Assessment of CFD in Reactor Safety Analysis. NUCL TECHNOL 2017. [DOI: 10.13182/nt11-a12514] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
11
Saeed M, Yu J, Abdalla AAA, Hou B, Hussain G, Zhong X. The effect of turbulence modeling on hydrogen jet dispersion inside a compartment space using the HYDRAGON code. J NUCL SCI TECHNOL 2017. [DOI: 10.1080/00223131.2017.1299645] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
12
Sun L, Peng M, Xia G, Lv X, Li R. Numerical Study on Coolant Flow Distribution at the Core Inlet for an Integral Pressurized Water Reactor. NUCLEAR ENGINEERING AND TECHNOLOGY 2017. [DOI: 10.1016/j.net.2016.07.005] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
13
Shams A, Damiani G, Rosa D, Komen E. Design of a single-phase PTS numerical experiment for a reference Direct Numerical Simulation. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.01.038] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
14
Bucalossi A, Moretti F, Melideo D, Del Nevo A, D’Auria F, Höhne T, Lisenkov E, Gallori D. Experimental investigation of in-vessel mixing phenomena in a VVER-1000 scaled test facility during unsteady asymmetric transients. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.05.005] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
15
Loginov M, Komen E, Höhne T. Application of large-eddy simulation to pressurized thermal shock: Assessment of the accuracy. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.05.027] [Citation(s) in RCA: 11] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
16
Pigny SL. Academic validation of multi-phase flow codes. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2010.08.007] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
17
Jamet D, Lebaigue O, Morel C, Arcen B. Towards a multi-scale approach of two-phase flow modeling in the context of DNB modeling. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2009.11.034] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
18
Smith BL. ASSESSMENT OF CFD CODES USED IN NUCLEAR REACTOR SAFETY SIMULATIONS. NUCLEAR ENGINEERING AND TECHNOLOGY 2010. [DOI: 10.5516/net.2010.42.4.339] [Citation(s) in RCA: 24] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
19
Jeong JJ, Yoon HY, Park IK, Cho HK, Lee HD. DEVELOPMENT AND PRELIMINARY ASSESSMENT OF A THREE-DIMENSIONAL THERMAL HYDRAULICS CODE, CUPID. NUCLEAR ENGINEERING AND TECHNOLOGY 2010. [DOI: 10.5516/net.2010.42.3.279] [Citation(s) in RCA: 31] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
20
Implementation of a second-order upwind method in a semi-implicit two-phase flow code on unstructured meshes. ANN NUCL ENERGY 2010. [DOI: 10.1016/j.anucene.2009.12.015] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
21
Khane V, Usman S. Further on integrator circuit analogy for natural convection. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2009.10.007] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
22
Paladino D, Zboray R, Benz P, Andreani M. Three-gas mixture plume inducing mixing and stratification in a multi-compartment containment. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2008.07.014] [Citation(s) in RCA: 23] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
23
Štrubelj L, Ézsöl G, Tiselj I. Direct contact condensation induced transition from stratified to slug flow. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2008.12.004] [Citation(s) in RCA: 26] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
24
de la Rosa J, Escrivá A, Herranz L, Cicero T, Muñoz-Cobo J. Review on condensation on the containment structures. PROGRESS IN NUCLEAR ENERGY 2009. [DOI: 10.1016/j.pnucene.2008.01.003] [Citation(s) in RCA: 88] [Impact Index Per Article: 5.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
25
A semi-implicit numerical scheme for transient two-phase flows on unstructured grids. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2008.08.017] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
26
Yadigaroglu G, Simiano M, Milenkovic R, Kubasch J, Milelli M, Zboray R, De Cachard F, Smith B, Lakehal D, Sigg B. CFD4NRS with a focus on experimental and CMFD investigations of bubbly flows. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.02.047] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
27
CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.02.038] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
28
CFD simulations of light gas release and mixing in the Battelle Model-Containment with CFX. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.02.042] [Citation(s) in RCA: 17] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
29
Andreani M, Haller K, Heitsch M, Hemström B, Karppinen I, Macek J, Schmid J, Paillere H, Toth I. A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines: A computational challenge. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.01.021] [Citation(s) in RCA: 24] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
30
Smith BL. A numerical investigation of three-dimensional flows in large volumes in the context of passive containment cooling in BWRs. NUCLEAR ENGINEERING AND DESIGN 2007. [DOI: 10.1016/j.nucengdes.2007.02.001] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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