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Vineet Kumar
Vineet Kumar
Verified email at ornl.gov - Homepage
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Cited by
Cited by
Year
Validation of RELAP5/MOD3. 3 for subcooled boiling, flashing and condensation in a vertical annulus
WD Fullmer, V Kumar, CS Brooks
Progress in Nuclear Energy 93, 205-217, 2016
302016
Experimental investigation of variability in bubble departure characteristics between nucleation sites in subcooled boiling flow
ZJ Ooi, V Kumar, JL Bottini, CS Brooks
International Journal of Heat and Mass Transfer 118, 327-339, 2018
282018
Influence of wettability due to laser-texturing on critical heat flux in vertical flow boiling
JL Bottini, V Kumar, S Hammouti, D Ruzic, CS Brooks
International Journal of Heat and Mass Transfer 127, 806-817, 2018
272018
Experimental database of two-phase natural circulation with local measurements
ZJ Ooi, V Kumar, CS Brooks
Progress in Nuclear Energy 116, 124-136, 2019
252019
Forced convection steam-water experimental database in a vertical annulus with local measurements
V Kumar, ZJ Ooi, CS Brooks
International Journal of Heat and Mass Transfer 137, 216-228, 2019
162019
CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pressurized water reactors
R Salko, A Wysocki, T Blyth, A Toptan, J Hu, V Kumar, C Dances, W Dawn, ...
Nuclear Engineering and Design 397, 111927, 2022
122022
Inter-group mass transfer modeling in the two-group two-fluid model with interfacial area transport equation in condensing flow
V Kumar, Brooks, C S.
International Journal of Heat and Mass Transfer 119, 688-703, 2018
112018
Innovative approaches for reducing CO2 emissions of aviation engines part 1: selection of promising approaches
V Kumar, P Panda, H Mongia, S Naik
10th International Energy Conversion Engineering Conference, 3954, 2012
112012
Validation and model sensitivity of the interfacial area transport equation in condensing flows
V Kumar, CS Brooks
International Journal of Heat and Mass Transfer 113, 647-661, 2017
92017
Validation of the interfacial area transport equation coupled with the void transport equation for prediction of flashing flows
ZJ Ooi, V Kumar, CS Brooks
Nuclear Science and Engineering 194 (8-9), 598-619, 2020
82020
Improvements to CTF Closure Models for Modelling of Two-Phase Flow
R Salko Jr, V Kumar, B Hizoum, W Gurecky
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
82020
Benchmark of interfacial area concentration approaches for the two-fluid model in gas-dispersed condensing flow
V Kumar, CS Brooks
Progress in Nuclear Energy 124, 103329, 2020
72020
Development of CTF modeling of interfacial drag, wall shear, and interfacial heat transfer for bubbly and annular-mist flow regimes
V Kumar, B Hizoum, R Salko Jr
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2021
62021
A Review of Computational Capabilities and Requirements in High-Resolution Simulation of Nonferrous Pyrometallurgical Furnaces
A Anderson, V Kumar, VM Rao, J Grogan
JOM 74 (4), 1543-1567, 2022
52022
Implementation of a new wall boiling model in ctf
V Kumar, R Salko Jr
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
52020
Ctf improved drag model and flow regime transition criteria
B Hizoum, V Kumar, R Salko Jr
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2022
42022
Thermal loading analysis of the ring injection dump for the Spallation Neutron Source facility
V Kumar, M Harvey, M Wendel, P Jain, NJ Evans
Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2021
32021
Conceptual design of aeropropulsion engine heat exchangers Part 1: micro channels and selection of advanced configurations
P Panda, V Kumar, H Mongia
51st AIAA Aerospace Sciences Meeting Including the New Horizons Forum and …, 2013
32013
Sister Rod Destructive Examinations (FY22) Appendix I: SNF Aerosols Released During Rod Fracture
R Montgomery, Y Sasikumar, TT Keever, V Kumar
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2023
22023
Improvement of two-phase closure models in CTF using Bayesian inference
V Kumar, W Gurecky, R Salko, B Hizoum
Nuclear Engineering and Design 398, 111968, 2022
22022
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