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Dasari V. Rao
Observed names:
D. Rao,
D. V. Rao,
D.V. Rao,
DASARI RAO,
DASARI V. RAO,
Dasari Rao
show all 6
Institutions:
Los Alamos National Laboratory,
Civilian Nuclear Programs
Observed institutions:
Los Alamos National Laboratory,
University of New Mexico,
Civilian Nuclear Programs,
Indian Institute of Technology Kanpur
OpenAlex ID:
A5111603145
Elastic moduli of high-density, sintered monoliths of yttrium dihydride
2020
·
A.P. Shivprasad
, D.M. Frazer
, et al.
·
Journal of Alloys and Compounds
·
70
On the Predictions of Critical Heat Flux in Rod Bundles at Low Flow and Low Pressure Conditions
1991
·
MOHAMED S. EL-GENK
, DASARI RAO
·
Heat Transfer Engineering
·
56
Advancements in Yttrium Hydride Moderator Development
2022
·
Holly Trellue
, Chase Taylor
, et al.
·
Nuclear Technology
·
37
Development of effective thermal conductivity model for particle-type nuclear fuels randomly distributed in a matrix
2018
·
Maolong Liu
, Youho Lee
, et al.
·
Journal of Nuclear Materials
·
33
A density functional theory and neutron diffraction study of the ambient condition properties of sub-stoichiometric yttrium hydride
2021
·
Vedant K. Mehta
, Sven C. Vogel
, et al.
·
Journal of Nuclear Materials
·
26
Buoyancy induced instability of laminar flows in vertical annuli—I. Flow visualization and heat transfer experiments
1990
·
Mohamed S. El-Genk
, Dasari V. Rao
·
International Journal of Heat and Mass Transfer
·
26
Evaluation of Yttrium Hydride (δ-YH2-x) Thermal Neutron Scattering Laws and Thermophysical Properties
2021
·
Vedant K. Mehta
, Michael W. D. Cooper
, et al.
·
Nuclear Science and Engineering
·
21
Development of a two-regime heat conduction model for TRISO-based nuclear fuels
2019
·
Maolong Liu
, Jared Thurgood
, et al.
·
Journal of Nuclear Materials
·
21
Forced and combined convection of water in a vertical seven-rod bundle with P/D = 1.38
1990
·
Mohamed S. El-Genk
, Shokry D. Bedrose
, et al.
·
International Journal of Heat and Mass Transfer
·
16
Heat Transfer Experiments and Correlations for Low-Reynolds-Number Flows of Water in Vertical Annuli
1989
·
MOHAMED S. EL-GENK
, DASARI V. RAO
·
Heat Transfer Engineering
·
16
A Deployable 40 kWe Lunar Fission Surface Power Concept
2022
·
Steven Oleson
, Thomas Packard
, et al.
·
Nuclear and Emerging Technologies for Space (NETS)
·
14
Special Purpose Application Reactors: Systems Integration Decision Support
2018
·
John Kennedy
, Piyush Sabharwall
, et al.
·
14
PDF
Capturing multiphysics effects in hydride moderated microreactors using MARM
2022
·
Vedant K. Mehta
, Jerawan Armstrong
, et al.
·
Annals of Nuclear Energy
·
13
Key Performance Parameters for MW-Class NEP Elements and their Interfaces
2022
·
Matthew E. Duchek
, William Machemer
, et al.
·
AIAA Accelerating Space Commerce, Exploration, and New Discovery Conference (ASCEND)
·
10
Buoyancy induced instability of laminar flows in vertical annuli—II. Model development and analysis
1990
·
Dasari V. Rao
, Mohamed S. El-Genk
·
International Journal of Heat and Mass Transfer
·
10
Nuclear Electric Propulsion Brayton Power Conversion Working Fluid Considerations
2022
·
Rodger Dyson
, D. Rao
, et al.
·
Nuclear and Emerging Technologies for Space (NETS)
·
9
Salt-Cooled Modular Innovative Thorium Heavy Water-Moderated Reactor System
2013
·
Holly R. Trellue
, Richard J. Kapernick
, et al.
·
Nuclear Technology
·
8
Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor
2024
·
Vedant K. Mehta
, Aditya P. Shivprasad
, et al.
·
Nuclear Technology
·
5
Heat Pipe Heat Exchanger for Nuclear Electric Propulsion Power Conversion System
2022
·
Daria Nikitaeva
, Corey D. Smith
, et al.
·
AIAA Accelerating Space Commerce, Exploration, and New Discovery Conference (ASCEND)
·
5
Microreactors: A Technology Option for Accelerated Innovation [Slides]
2020
·
Dasari Rao
, USDOE Office of Nuclear Energy (NE)
, et al.
·
4
PDF
Database of Previous Research Supporting Microreactor Designs
2018
·
Piyush Sabharwall
, Patrick McClure
, et al.
·
2
Accumulation and Head-Loss Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris
2006
·
Ashok K. Ghosh
, Arup K. Maji
, et al.
·
Nuclear Technology
·
2
Thermal hydraulics model for Sandia's annular core research reactor
1988
·
D.V. Rao
, Mohamed S. El‐Genk
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
2
Steam-generator simulation with non-equilibrium two-phase flow models
1986
·
P. Munshi
, K.S. Ram
, et al.
·
Annals of Nuclear Energy
·
2
Feasibility of Using Poisons to Suppress the Positive Temperature Reactivity Coefficient in Hydride-Moderated Reactors
2023
·
Vedant K. Mehta
, Zachary A. Miller
, et al.
·
Nuclear Science and Engineering
·
1
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Works count:
48
Citation count:
429
H-index:
13
I10-index:
15
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