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- Higher education (4)
- Radioactive wastes (4)
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- Transmutation Research Program (4)
- Advanced Fuel Cycle Initiative (U.S.) (2)
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- Accelerator-driven systems; Bremsstrahlung; Nuclear fission; Nuclear reactions; Neutrons; Photons; Transmutation (Chemistry) (1)
- Actinide elements – Separation; Radioactive wastes — Purification; Reactor fuel reprocessing; Spent reactor fuels (1)
- Actinide elements; Mixed oxide fuels (Nuclear engineering); Nitrides; Nuclear chemistry; Nuclear fuels; Solid oxide fuel cells; Transmutation (Chemistry); Uranium (1)
- Aluminum silicates (1)
- Barium (1)
- Ceramics (1)
- Cesium (1)
- Erbium (1)
- Global Nuclear Energy Partnership (1)
- Heavy-ion physics (1)
- Magnesium oxide (1)
- Mixed oxide fuels (Nuclear engineering) (1)
- Mixed oxide fuels (Nuclear engineering); Nuclear chemistry; Nuclear fuels; Solid oxide fuel cells; Transmutation (Chemistry) (1)
- Monte Carlo method; Nuclear reactors; Radiation — Dosage; Radiation dosimetry; Shielding (Radiation); Statistics (1)
- Nuclear chemistry (1)
- Nuclear fuels (1)
- Nuclear reactors; Monte Carlo method; Spent reactor fuels; Stochastic processes (1)
- Plutonium (1)
- Radioactive wastes—Storage (1)
- Radioactive wastes—Storage; Radioactive wastes — Transmutation; Technetium compounds; Technetium — Isotopes; Zirconium alloys (1)
- Secondary neutron cross section measurements (1)
- Solid oxide fuel cells (1)
- Strontium (1)
- Zirconium oxide (1)
Articles 1 - 14 of 14
Full-Text Articles in Nuclear Engineering
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 …
Gnep Quarterly Input – Unlv July 1 Through September 30, 2007, Harry Reid Center For Environmental Studies. Nuclear Science And Technology Division
Gnep Quarterly Input – Unlv July 1 Through September 30, 2007, Harry Reid Center For Environmental Studies. Nuclear Science And Technology Division
Transmutation Research Program Reports (TRP)
Quarterly report highlighting research projects, activities and objectives of the Transmutation Research Program at the Nuclear Science & Technology Division, Harry Reid Research Center.
The University of Nevada, Las Vegas supports the Global Nuclear Energy Partnership (GNEP) through research and development of technologies for economic and environmentally sound refinement of spent nuclear fuel. The UNLV program has four components: infrastructure, international collaboration, student-based research, and management and program support.
Afci Quarterly Input – Unlv April 1 Through June 30, 2007, Harry Reid Center For Environmental Studies. Nuclear Science And Technology Division
Afci Quarterly Input – Unlv April 1 Through June 30, 2007, Harry Reid Center For Environmental Studies. Nuclear Science And Technology Division
Transmutation Research Program Reports (TRP)
Quarterly report highlighting research projects, activities and objectives of the Transmutation Research Program at the Nuclear Science & Technology Division, Harry Reid Research Center.
The University of Nevada, Las Vegas supports the AFCI through research and development of technologies for economic and environmentally sound refinement of spent nuclear fuel. The UNLV program has four components: infrastructure, international collaboration, student-based research, and management and program support.
Afci Quarterly Input – Unlv January 1 Through March 31, 2007, Harry Reid Center For Environmental Studies. Nuclear Science And Technology Division
Afci Quarterly Input – Unlv January 1 Through March 31, 2007, Harry Reid Center For Environmental Studies. Nuclear Science And Technology Division
Transmutation Research Program Reports (TRP)
Quarterly report highlighting research projects, activities and objectives of the Transmutation Research Program at the Nuclear Science & Technology Division, Harry Reid Research Center.
The University of Nevada, Las Vegas supports the AFCI through research and development of technologies for economic and environmentally sound refinement of spent nuclear fuel. The UNLV program has four components: infrastructure, international collaboration, student-based research, and management and program support.
Secondary Neutron-Production Cross Sections From Heavy-Ion Interactions Between 230 And 600 Mev/Nucleon, Lawrence H Heilbronn
Secondary Neutron-Production Cross Sections From Heavy-Ion Interactions Between 230 And 600 Mev/Nucleon, Lawrence H Heilbronn
Faculty Publications and Other Works -- Nuclear Engineering
Secondary neutron-production cross-sections have been measured from interactions of 230 MeV/nucleon He, 400 MeV/nucleon N, 400 MeV/nucleon Kr, 400 MeV/nucleon Xe, 500 MeV/nucleon Fe, and 600 MeV/nucleon Ne interacting in a variety of elemental and composite targets. We report the double-differential production cross sections, angular distributions, energy spectra, and total cross sections from all systems. Neutron energies were measured using the time-of-flight technique, and were measured at laboratory angles between 5° and 80°. The spectra exhibit behavior previously reported in other heavy-ion-induced neutron production experiments; namely, a peak at forward angles near the energy corresponding to the beam velocity, with …
Evaluation Of Cs/Sr Waste Form For Long Term Storage And Disposal, Gary Cerefice, Longzhou Ma
Evaluation Of Cs/Sr Waste Form For Long Term Storage And Disposal, Gary Cerefice, Longzhou Ma
Waste Forms Campaign (TRP)
The goal of this project is to examine two potential concerns regarding the long-term performance of a proposed cesium/ strontium waste form. To facilitate long-term storage, up to 300 years, the disposal containers will need to be able to survive for the entire storage interval. The first aspect of the project will explore the potential interaction of the aluminosilicate waste form with the storage canister materials to determine if there is any corrosion or chemical interaction concerns for the storage of the materials.
At the end of the storage interval, most of the 137Cs in the waste form will have …
Separation Of Technetium From Uranium And Waste Form Synthesis, Kenneth Czerwinski
Separation Of Technetium From Uranium And Waste Form Synthesis, Kenneth Czerwinski
Waste Forms Campaign (TRP)
In this project, systematic investigations on the Tc-Zr binary metal system will be evaluated for the first time. The synthesis of metallic Tc as well as its alloys with Zr will be evaluated. In order to provide valuable data to AFC R&D, the thermodynamic equilibrium phases, as well as their performance under repository conditions, will be examined.
Reactor Physics Studies For The Afci Reactor-Accelerator Coupling Experiments Project, Denis Beller
Reactor Physics Studies For The Afci Reactor-Accelerator Coupling Experiments Project, Denis Beller
Transmutation Sciences Physics (TRP)
The specific research objective of this three-year project is to design and conduct accelerator driven experiments, which will help demonstrate in the U.S. the ability to design, compute, and conduct ADSS experiments and to predict and measure source importance, coupling efficiency, sub-critical reactor kinetics and source-driven transients. In addition, databases will be created for both steady state and transient ADSS experiments for the nuclear community to develop and test new computational codes and methods, and the importance of a driving neutron source in various regions of different subcritical assemblies will be mapped. Experiments will be conducted and compared to calculations …
Combined Radiation Detection Methods For Assay Of Higher Actinides In Separation Processes, Denis Beller, Warnick Kernan
Combined Radiation Detection Methods For Assay Of Higher Actinides In Separation Processes, Denis Beller, Warnick Kernan
Safeguards Campaign (TRP)
The ultimate objective of this project is to develop technology to detect and accurately measure quantities of higher actinides in processing systems without taking frequent samples. These systems include used fuel receipt, separations batches, and pipelines. A variety of measurements may be combined to calculate flow rates of actinide elements with a to-be-determined precision. Nuclear and decay characteristics of materials during processing will be acquired, conceptual designs of monitoring systems will be developed, radiation transport studies will be conducted to develop an understanding of operational regimes, and experiments will be performed to confirm performance. Radiation transport and scoping studies will …
Dissolution, Reactor, And Environmental Behavior Of Zro2-Mgo Inert Fuel Matrix, Kenneth Czerwinski
Dissolution, Reactor, And Environmental Behavior Of Zro2-Mgo Inert Fuel Matrix, Kenneth Czerwinski
Fuels Campaign (TRP)
This project will examine inert fuels containing ZrO2 and MgO as the inert matrix. Ceramics with this inert matrix, Ce, U and eventually Pu will be synthesized and examined. While the Advanced Fuel Cycle Initiative focus is on inert fuels with Pu as the fissile component, this task will perform initial laboratory experiments with Ce and U. The initial work with Ce will be performed early in the project with results used as a basis for U studies. Reactor physics calculations will be used to examine suitable quantities of burnable poisons from the candidate elements Gd, Er, or Hf. …
Impact Of The Synthesis Process On Structure Properties For Afci Fuel Candidates, Kenneth Czerwinski
Impact Of The Synthesis Process On Structure Properties For Afci Fuel Candidates, Kenneth Czerwinski
Fuels Campaign (TRP)
Synthesis of actinium mononitrides using carbothermic reduction of the corresponding oxides has a few outstanding issues, including the formation of secondary phases such as oxides and carbides and low densities of the final product. Furthermore the requirement of a high process temperature at 1700°C, for more than 12 hours is also a drawback particularly for Americium-bearing samples. Therefore, it is important to explore the use of other possible routes to synthesize actinide mononitrides.
A low temperature process is used in this research to produce actinide mononitrides using a fluoride route in which the first step is to mix the actinide …
Solution-Based Synthesis Of Nitride Fuels, Tyler A. Sullens, Kenneth Czerwinski
Solution-Based Synthesis Of Nitride Fuels, Tyler A. Sullens, Kenneth Czerwinski
Fuels Campaign (TRP)
The preliminary studies into the synthesis of actinide nitride fuels through a low temperature, liquid ammonia based synthesis route have been conducted on the uranium containing system, and there is good indication for the success of synthesizing uranium (III) nitride. The dissolution of iodine in ammonia is a rapid process, resulting in a pale green solution, which does not result in any observable oxidation of iodine. The cannula transfer of dissolved iodine into the reaction vessel containing U metal has been conducted with little to no residual iodine remaining in the original flask. The metal being used for these reactions …
University Of Nevada, Las Vegas Transmutation Research Program Annual Report Academic Year 2006-2007, Anthony Hechanova, Rebecca Arbour
University Of Nevada, Las Vegas Transmutation Research Program Annual Report Academic Year 2006-2007, Anthony Hechanova, Rebecca Arbour
Transmutation Research Program Reports (TRP)
It is my pleasure to present the UNLV Transmutation Research Program’s sixth annual report that highlights the academic year 2006-2007. Supporting this document are the many technical reports and theses that have been generated over the past five years.
In the sixth year of our program, we continued to see growth in the Radiochemistry Ph.D. program with a total of 13 students in the third year of the program (we anticipated eight in the program proposal). Since our inception, the program has sponsored to their conclusion 42 M.S. and 4 Ph.D. degrees. The program supported 39 graduate students, 17 undergraduates, …