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- Climatic changes – Mathematical models (2)
- Monte Carlo method; Nuclear reactors; Radiation — Dosage; Radiation dosimetry; Shielding (Radiation); Statistics (2)
- Nuclear reactors; Monte Carlo method; Spent reactor fuels; Stochastic processes (2)
- China; Dust storms – Forecasting; Mathematical models; Sandstorms – Forecasting; Statistics (1)
- Climatic changes – Computer simulation (1)
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Articles 1 - 9 of 9
Full-Text Articles in Statistics and Probability
Estimation Of Performance Indices For The Planning Of Sustainable Transportation Systems, Pankaj Maheshwari, Alexander Paz, Pushkin Kachroo
Estimation Of Performance Indices For The Planning Of Sustainable Transportation Systems, Pankaj Maheshwari, Alexander Paz, Pushkin Kachroo
Graduate Publications & Presentations
What is sustainable transportation system?
Fulfill the needs of current generations without compromising the ability of future generations
Utilize resources without compromising their health and productivity Leads to development that improves quality of life
Assimilate economic, ecological, social, and bio-physical components of resource ecosystems
Minimize the use of renewable and non-renewable resources, provide affordability and equity between generations
A Statistical Model For Long-Term Forecasting Of Strong Sand Dust Storms, Siqi Tan
A Statistical Model For Long-Term Forecasting Of Strong Sand Dust Storms, Siqi Tan
UNLV Theses, Dissertations, Professional Papers, and Capstones
Dust elevated into the atmosphere by dust storms has numerous environmental consequences. These include contributing to climate change; modifying local weather conditions; producing chemical and biological changes in the oceans; and affecting soil formation, surface water, groundwater quality, crop growth, and survival (Goudie and Middleton, 1992). Societal impacts include disruptions to air, road and rail traffic; interruption of radio services; the myriad effects of static-electricity generation; property damage; and health effects on humans and animals (Warner, 2004).
In this thesis, we extend the idea of empirical recurrence rate (ERR), developed by Ho (2008), to model the temporal trend of the …
Research Poster: Hydrological Impacts Of Climate Change On Colorado Basin, Peng Jiang, Zhongbo Yu
Research Poster: Hydrological Impacts Of Climate Change On Colorado Basin, Peng Jiang, Zhongbo Yu
2010 Annual Nevada NSF EPSCoR Climate Change Conference
Research poster
Research Poster: An Overview Of Progress In Nsf Epscor Project Entitled, “Reducing Cloud Uncertainties In Climate Models”, Subhashree Mishra, David L. Mitchell, W. Patrick Arnott
Research Poster: An Overview Of Progress In Nsf Epscor Project Entitled, “Reducing Cloud Uncertainties In Climate Models”, Subhashree Mishra, David L. Mitchell, W. Patrick Arnott
2010 Annual Nevada NSF EPSCoR Climate Change Conference
Research poster
Research Poster: Climate Prediction Downscaling Of Temperature And Precipitation In The Great Basin Region, Ramesh Vellore, Benjamin J. Hatchett, Darko Koracin
Research Poster: Climate Prediction Downscaling Of Temperature And Precipitation In The Great Basin Region, Ramesh Vellore, Benjamin J. Hatchett, Darko Koracin
2010 Annual Nevada NSF EPSCoR Climate Change Conference
Research poster
Implementation Of Uncertainty Propagation In Triton/Keno, Charlotta Sanders, Denis Beller
Implementation Of Uncertainty Propagation In Triton/Keno, Charlotta Sanders, Denis Beller
Reactor Campaign (TRP)
Monte Carlo methods are beginning to be used for three dimensional fuel depletion analyses to compute various quantities of interest, including isotopic compositions of used nuclear fuel. The TRITON control module, available in the SCALE 5.1 code system, can perform three-dimensional (3-D) depletion calculations using either the KENO V.a or KENO-VI Monte Carlo transport codes, as well as the two-dimensional (2-D) NEWT discrete ordinates code. To overcome problems such as spatially nonuniform neutron flux and non-uniform statistical uncertainties in computed reaction rates and to improve the fidelity of calculations using Monte Carlo methods, uncertainty propagation is needed for depletion calculations.
Monaco/Mavric Evaluation For Facility Shielding And Dose Rate Analysis, Charlotta Sanders, Denis Beller
Monaco/Mavric Evaluation For Facility Shielding And Dose Rate Analysis, Charlotta Sanders, Denis Beller
Reactor Campaign (TRP)
The dimensions and the large amount of shielding required for Global Nuclear Energy Partnership (GNEP) facilities, advanced radiation shielding, and dose computation techniques are beyond today’s capabilities and will certainly be required. With the Generation IV Nuclear Energy System Initiative, it will become increasingly important to be able to accurately model advanced Boiling Water Reactor and Pressurized Water Reactor facilities, and to calculate dose rates at all locations within a containment (e.g., resulting from radiations from the reactor as well as the from the primary coolant loop) and adjoining structures (e.g., from the spent fuel pool).
The MAVRIC sequence is …
Implementation Of Uncertainty Propagation In Triton/Keno: To Support The Global Nuclear Energy Partnership, Charlotta Sanders, Denis Beller
Implementation Of Uncertainty Propagation In Triton/Keno: To Support The Global Nuclear Energy Partnership, Charlotta Sanders, Denis Beller
Reactor Campaign (TRP)
Monte Carlo methods are beginning to be used for three-dimensional fuel depletion analyses to compute various quantities of interest, including isotopic compositions of used fuel.1 The TRITON control module, available in the SCALE 5.1 code system, can perform three dimensional (3-D) depletion calculations using either the KENO V.a or KENO-VI Monte Carlo transport codes, as well as the two-dimensional (2- D) NEWT discrete ordinates code. For typical reactor systems, the neutron flux is not spatially uniform. For Monte Carlo simulations, this results in non-uniform statistical uncertainties in the computed reaction rates. For spatial regions where the flux is low, e.g., …
Monaco/Mavric Evaluation For Facility Shielding And Dose Rate Analysis: To Support The Global Nuclear Energy Partnership, Charlotta Sanders, Denis Beller
Monaco/Mavric Evaluation For Facility Shielding And Dose Rate Analysis: To Support The Global Nuclear Energy Partnership, Charlotta Sanders, Denis Beller
Reactor Campaign (TRP)
Monte Carlo methods are used to compute fluxes or dose rates over large areas using mesh tallies. For problems that demand that the uncertainty in each mesh cell be less than some set maximum, computation time is controlled by the cell with the largest uncertainty. This issue becomes quite troublesome in deep-penetration problems, and advanced variance reduction techniques are required to obtain reasonable uncertainties over large areas.
In this project the MAVRIC sequence will be evaluated along with the Monte Carlo engine Monaco to investigate its effectiveness and usefulness in facility shielding and dose rate analyses. A previously MCNP-evaluated cask …