Research Output 1986 2017

2009

3-D virtual reality for education, training and improved human performance in nuclear applications

Xi, C., Wu, H., Joher, A., Kirsch, L., Luo, C., Khasawneh, M. & Rizwan-uddin 2009 6th American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2009. Vol. 4, p. 2347-2356 10 p.

Research output: ResearchConference contribution

Virtual reality
Education
Computer programming languages

A lattice Boltzmann framework to simulate boiling water reactor core hydrodynamics

Jain, P. K., Tentner, A. & Rizwan-uddin Sep 2009 In : Computers and Mathematics with Applications. 58, 5, p. 975-986 12 p.

Research output: Research - peer-reviewArticle

Lattice Boltzmann
Reactor
Hydrodynamics
Water
Framework

Analytical solution to transient asymmetric heat conduction in a multilayer annulus

Jain, P. K., Singh, S. & Rizwan-uddin Jan 2009 In : Journal of Heat Transfer. 131, 1, p. 1-7 7 p.

Research output: Research - peer-reviewArticle

annuli
conductive heat transfer
eigenvalues
Heat conduction
Multilayers

A new turbulence model for porous media flows. Part I: Constitutive equations and model closure

Teruel, F. E. & Rizwan-uddin Sep 1 2009 In : International Journal of Heat and Mass Transfer. 52, 19-20, p. 4264-4272 9 p.

Research output: Research - peer-reviewArticle

turbulence models
constitutive equations
closures
Constitutive equations
Constitutive models
turbulence models
turbulence
simulation
Turbulence models
Porous materials

An innovative research reactor design

Teruel, F. E. & Rizwan-uddin Feb 2009 In : Nuclear Engineering and Design. 239, 2, p. 395-407 13 p.

Research output: Research - peer-reviewArticle

reactor design
Research reactors
reactor
Hot Temperature
Fluxes

A nodal integral method for quadrilateral elements

Nezami, E. G., Singh, S., Sobh, N. & Uddin, R. Sep 20 2009 In : International Journal for Numerical Methods in Fluids. 61, 2, p. 144-164 21 p.

Research output: Research - peer-reviewArticle

Quadrilateral Element
Integral Method
Mesh
Poisson equation
Brick
pressure drop
Reynolds number
permeability
turbulence
porosity

Fission gas production in reactor fuels

Hu, J., Hayes, A. C. & Rizwan-uddin 2009 In : Transactions of the American Nuclear Society. 100, p. 629-630 2 p.

Research output: Research - peer-reviewArticle

k-ε modeling using modified nodal integral method

Singh, S. & Rizwan-uddin Jul 2009 In : Nuclear Engineering and Design. 239, 7, p. 1314-1322 9 p.

Research output: Research - peer-reviewArticle

modeling
method
simulation
Reynolds number
turbulent flow

Lattice boltzmann simulation of liquid drop coalescence driven by surface tension

Jain, P. K., Tentner, A. & Rizwan-Uddin 2009 In : Transactions of the American Nuclear Society. 101, p. 870-873 4 p.

Research output: Research - peer-reviewArticle

Material flow simulation in an international fuel supply model

Taylor, J. T. P., Rizwan-uddin & Jacobson, J. 2009 In : Transactions of the American Nuclear Society. 100, p. 159-160 2 p.

Research output: Research - peer-reviewArticle

Modified nodal integral method incorporated with irregular-shape elements for Navier-Stokes equations

Huang, K. & Rizwan-Uddin 2009 American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009. Vol. 4, p. 2243-2254 12 p.

Research output: ResearchConference contribution

Integral Method
Irregular
Navier-Stokes Equations
Navier-Stokes equation
Navier Stokes equations
2008

A coupled CFD-system code development and application

Yan, Y., Rizwan-uddin & Kim, K. 2008 International Conference on the Physics of Reactors 2008, PHYSOR 08. Vol. 3, p. 1992-1999 8 p.

Research output: ResearchConference contribution

Computational fluid dynamics
Dynamical systems
computational fluid dynamics
Hot Temperature
hydraulics

A lattice boltzmann framework for the simulation of boiling hydrodynamics in BWRs

Jain, P. K., Tentner, A. & Rizwan-uddin 2008 In : Transactions of the American Nuclear Society. 98, p. 446-448 3 p.

Research output: Research - peer-reviewArticle

Analytical solution to transient heat conduction in polar coordinates with multiple layers in radial direction

Singh, S., Jain, P. K. & Rizwan-uddin Mar 2008 In : International Journal of Thermal Sciences. 47, 3, p. 261-273 13 p.

Research output: Research - peer-reviewArticle

polar coordinates
conductive heat transfer
eigenvalues
Heat conduction
boundary conditions

A secure novel sensor fusion architecture for nuclear applications

Khasawneh, M., Rizwan-Uddin, Malkawi, M. I., Hayajneh, T. & Almalkawi, M. 2008 Proceeding of the 5th International Symposium on Mechatronics and its Applications, ISMA 2008. 4648860

Research output: ResearchConference contribution

Sensors
Radiation
Nuclear industry
Decision making
Control systems

Coupled neutronics and thermal-hydraulics simulations using MCNP and FLUENT

Hu, J. & Rizwan-uddin 2008 In : Transactions of the American Nuclear Society. 98, p. 606-608 3 p.

Research output: Research - peer-reviewArticle

Innovative training tools for improved human performance

Xi, C., Khasawneh, M. & Uddin, R. 2008 American Nuclear Society - Conference on Nuclear Training and Education, CONTE 2009. p. 101-102 2 p.

Research output: ResearchConference contribution

K-E modeling using modified nodal integral method

Singh, S. & Rizwanuddin 2008 American Nuclear Society - International Conference on Advances in Nuclear Power Plants, ICAPP 2008. Vol. 3, p. 1832-1842 11 p.

Research output: ResearchConference contribution

Reynolds number
Turbulent flow
Nuclear reactors
Laminar flow

Live webcast of a nuclear engineering laboratory

Uddin, R. & Wu, H. 2008 American Nuclear Society - Conference on Nuclear Training and Education, CONTE 2009. p. 105-106 2 p.

Research output: ResearchConference contribution

Numerical analysis of supercritical flow instabilities in a natural circulation loop

Jain, P. K. & Rizwan-uddin Aug 2008 In : Nuclear Engineering and Design. 238, 8, p. 1947-1957 11 p.

Research output: Research - peer-reviewArticle

supercritical flow
numerical analysis
analysis
thresholds
fluid
2007

A 3D, parallel LBM to simulate gravity driven bubbly and slug flows

Jain, P. K. & Rizwan-uddin 2007 In : Transactions of the American Nuclear Society. 97, p. 765-767 3 p.

Research output: Research - peer-reviewArticle

A web-based nuclear simulator using RELAP5 and LabVIEW

Kim, K. D. & Rizwan-uddin Jun 2007 In : Nuclear Engineering and Design. 237, 11, p. 1185-1194 10 p.

Research output: Research - peer-reviewArticle

simulators
simulator
Simulators
output
estimates

BWR stability and bifurcation analysis using reduced order models and system codes: Identification of a subcritical Hopf bifurcation using RAMONA

Dokhane, A., Hennig, D., Rizwan-uddin & Chawla, R. Oct 2007 In : Annals of Nuclear Energy. 34, 10, p. 792-802 11 p.

Research output: Research - peer-reviewArticle

bifurcation
analysis
code
Hopf bifurcation
Identification (control systems)

Comparison analysis of KENO.VI and MCNP-X codes for fast Reactor Assembly

Caro, J. M. & Rizwan-Uddin 2007 In : Transactions of the American Nuclear Society. 96, p. 825-826 2 p.

Research output: Research - peer-reviewArticle

Sodium

Effects of nanofluid coolant in a class 8 truck engine

Saripella, S. K., Yu, W., Routbort, J. L., France, D. M. & Rizwan-Uddin 2007 Non-Conference Specific Technical Papers - 2007, WONLY 2007.

Research output: ResearchConference contribution

Coolants
Trucks
Ethylene glycol
Water
Radiators

Interpretation of in-phase and out-of-phase BWR oscillations using an extended reduced order model and semi-analytical bifurcation analysis

Dokhane, A., Hennig, D., Rizwan-uddin & Chawla, R. Apr 2007 In : Annals of Nuclear Energy. 34, 4, p. 271-287 17 p.

Research output: Research - peer-reviewArticle

bifurcation
oscillation
analysis
Hopf bifurcation
Polycyclic aromatic hydrocarbons

Lattice Boltzmann Method (LBM) for nuclear engineering applications

Jain, P. & Rizwan-Uddin 2007 In : Transactions of the American Nuclear Society. 96, p. 595-597 3 p.

Research output: Research - peer-reviewArticle

Modeling of ANL small modular fast reactor

Hu, J. & Rizwan-uddin 2007 In : Transactions of the American Nuclear Society. 96, p. 647-648 2 p.

Research output: Research - peer-reviewArticle

Simulation of chaotic ABC flow using parallel modified nodal integral method

Singh, S. & Rizwan-uddin 2007 Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007.

Research output: ResearchConference contribution

Integral Method
Simulation
Beltrami flow
simulation
Fourier Method

Three-dimensional, virtual, game-like environments for education and training

Dixon, J., Markidis, S., Luo, C., Reynolds, J. & Rizwan-uddin 2007 In : Transactions of the American Nuclear Society. 97, p. 915-917 3 p.

Research output: Research - peer-reviewArticle

2006

Alternative modeling for turbulent flow in porous media

Teruel, F. E. & Rizwan-Uddin 2006 2006 ASME Joint U.S.-European Fluids Engineering Summer Meeting, FEDSM 2006. Vol. 2006

Research output: ResearchConference contribution

Turbulent flow
Turbulence models
Turbulence
Decomposition
Fluids

Alternative modeling for turbulent flow in porous media

Teruel, F. E. & Rizwan-uddin 2006 Proceedings of ASME Fluids Engineering Division Summer Meeting 2006, FEDSM2006. Vol. 1 SYMPOSIA, p. 849-857 9 p.

Research output: ResearchConference contribution

Turbulent flow
Turbulence models
Turbulence
Decomposition
Fluids

A nodal integral method for neutron diffusion equation in polar coordinates

Singh, S. & Rizwan-Uddin 2006 In : Transactions of the American Nuclear Society. 95, p. 817-819 3 p.

Research output: Research - peer-reviewArticle

A virtual control room with an embedded, interactive nuclear reactor simulator

Markidis, S. & Rizwan-uddin 2006 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006). Vol. 2006, p. 675-679 5 p.

Research output: ResearchConference contribution

Nuclear reactor simulators
Virtual reality
Textures
Computer applications
Power plants
Broadcasting
Internet
Experiments
Plasmas
Communication

Detailed core design and flow coolant conditions for neutron flux maximization in research reactors

Teruel, F. E. & Rizwan-Uddin 2006 Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14. Vol. 2006

Research output: ResearchConference contribution

Research reactors
Neutron flux
Coolants
Hot Temperature

Distance reactor laboratory and virtual tours

Edwards, E., Sweet, A., Blanchard, M., Agasie, R., Jain, P. & Rizwan-Uddin 2006 In : Transactions of the American Nuclear Society. 94, p. 33-35 3 p.

Research output: Research - peer-reviewArticle

Effects of modeling assumptions on BWR stability results

Bindra, H. & Rizwan-Uddin 2006 In : Transactions of the American Nuclear Society. 95, p. 748-750 3 p.

Research output: Research - peer-reviewArticle

Interactive virtual laboratory for distance education in nuclear engineering

Jain, P., Stubbins, J. & Uddin, R. 2006 PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics. Vol. 2006

Research output: ResearchConference contribution

Experiments
Internet
Plasmas
Communication

Modelling heat transfer in very high temperature gas cooled reactor

Singh, S. & Rizwan-Uddin 2006 Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14. Vol. 2006

Research output: ResearchConference contribution

Heat transfer
Natural convection
Coolants
Hot Temperature

Steady state and dynamic analyses of supercritical CO2 natural circulation loop

Jain, P. & Rizwan-uddin 2006 Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14. Vol. 2006

Research output: ResearchConference contribution

Conservation
Momentum

Turning points and sub- and supercritical bifurcations in a simple BWR model

Rizwan-Uddin Feb 2006 In : Nuclear Engineering and Design. 236, 3, p. 267-283 17 p.

Research output: Research - peer-reviewArticle

bifurcation
oscillation
parameter
oscillations
stable oscillations

Web- and system-code based, interactive, nuclear power plant simulators

Kim, K. D., Jain, P. & Rizwan-Uddin 2006 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006). Vol. 2006, p. 235-239 5 p.

Research output: ResearchConference contribution

Simulators
Web browsers
Graphical user interfaces
Computer programming languages
Students

Web-casting of nuclear reactor experiments

Jain, P., Markidis, S., Jones, B. G., Rizwan-Uddin, White, J. R. & Bobek, L. M. 2006 In : Transactions of the American Nuclear Society. 95, p. 994-996 3 p.

Research output: Research - peer-reviewArticle

2005

An integrated model of natural circulation loop under low pressure

Zhou, Q. & Rizwan-Uddin 2005 In : Transactions of the American Nuclear Society. 92, p. 782-784 3 p.

Research output: Research - peer-reviewArticle

Automated conversion of KENO input files to MCNP input files and comparison of KENO and MCNP results

Sugawara, K. & Rizwan-Uddin 2005 Monte Carlo 2005 Topical Meeting. p. 1523-1537 15 p.

Research output: ResearchConference contribution

Program translators
Geometry