Open Access. Powered by Scholars. Published by Universities.®
- Discipline
-
- Physical Sciences and Mathematics (32)
- Environmental Sciences (24)
- Oil, Gas, and Energy (24)
- Materials Science and Engineering (14)
- Nuclear (13)
-
- Physics (13)
- Mechanical Engineering (9)
- Chemistry (8)
- Metallurgy (8)
- Heat Transfer, Combustion (7)
- Radiochemistry (6)
- Electrical and Computer Engineering (2)
- Energy Systems (2)
- Statistical Methodology (2)
- Statistical Models (2)
- Statistics and Probability (2)
- Ceramic Materials (1)
- Computer Engineering (1)
- Computer Sciences (1)
- Controls and Control Theory (1)
- Electromagnetics and Photonics (1)
- Medicine and Health Sciences (1)
- Nanoscience and Nanotechnology (1)
- Occupational Health and Industrial Hygiene (1)
- Operations Research, Systems Engineering and Industrial Engineering (1)
- Physical Chemistry (1)
- Public Health (1)
- Robotics (1)
- Institution
- Keyword
-
- Radioactive wastes (8)
- Electric power production (5)
- Heat exchangers (5)
- Hydrogen as fuel (5)
- Nuclear energy (5)
-
- Nuclear reactors — Materials — Testing (5)
- Corrosion and anti-corrosives (4)
- Decomposition (Chemistry) (4)
- Eutectic alloys (4)
- Hazardous substances (4)
- Higher education (4)
- Lead-bismuth alloys (4)
- Nevada (4)
- Nevada – Nevada Test Site (4)
- Research (4)
- Risk assessment (4)
- Risk communication (4)
- Risk management (4)
- Transmutation Research Program (4)
- Steel — Corrosion (3)
- Sulfur (3)
- Advanced Fuel Cycle Initiative (U.S.) (2)
- Alloys – Testing (2)
- Cesium (2)
- Chromium alloys – Testing (2)
- Martensitic stainless steel (2)
- Metallurgy (2)
- Molybdenum alloys – Testing (2)
- Nuclear fuels (2)
- Accelerator-driven systems (1)
- Publication
-
- Fuels Campaign (TRP) (5)
- Publications (NSTD) (5)
- Reactor Campaign (TRP) (5)
- Transmutation Sciences Materials (TRP) (5)
- Nevada Risk Assessment/Management Program (4)
-
- Theses and Dissertations (4)
- Transmutation Research Program Reports (TRP) (4)
- Publications (YM) (3)
- Mechanical and Nuclear Engineering Publications (2)
- Waste Forms Campaign (TRP) (2)
- Masters Theses (1)
- Mechanical Engineering Faculty Research (1)
- Nuclear Engineering and Radiation Science Faculty Research & Creative Works (1)
- Safeguards Campaign (TRP) (1)
- Separations Campaign (TRP) (1)
- Transmutation Sciences Physics (TRP) (1)
- Publication Type
Articles 31 - 45 of 45
Full-Text Articles in Nuclear Engineering
Use Of Positron Annihilation Spectroscopy For Stress-Strain Measurements, Ajit K. Roy
Use Of Positron Annihilation Spectroscopy For Stress-Strain Measurements, Ajit K. Roy
Transmutation Sciences Materials (TRP)
During the past academic year, this project was focused on the characterization of residual stress in welded specimens consisting of austenitic and martensitic stainless steels using an activation technique based on the Positron Annihilation Spectroscopic (PAS) method. The extent of residual stress was expressed in terms of three line-shape parameters (S-, W- and T-). Further, efforts were made to characterize linear lattice defects such as dislocations in the vicinity of Fusion-Line (FL), Heat-Affected- Zone (HAZ), and the base material of the welded specimens using Transmission Electron Microscopy (TEM). The metallurgical microstructures at these three regions have also been evaluated by …
Fundamental And Applied Experimental Investigations Of Corrosion Of Steel By Lbe Under Controlled Conditions: Kinetics, Chemistry Morphology, And Surface Preparation, John Farley, Allen L. Johnson, Dale L. Perry
Fundamental And Applied Experimental Investigations Of Corrosion Of Steel By Lbe Under Controlled Conditions: Kinetics, Chemistry Morphology, And Surface Preparation, John Farley, Allen L. Johnson, Dale L. Perry
Transmutation Sciences Materials (TRP)
Advanced nuclear processes and facilities (e.g., transmutation of nuclear waste, fast reactors, and spallation neutron sources) impose special demands on materials, which must withstand high temperatures, high radiation fields, and chemical corrosion. Proposed schemes for transmuting nuclear waste require a nonmoderating coolant such as lead-bismuth eutectic (LBE). While LBE corrodes most steels, small amounts of oxygen in the LBE greatly reduces the corrosion rate, and could ideally re-grow a damaged oxide layer in-situ. The protective oxide layer would thus be self-healing. However, the fundamental understanding of the role of oxygen and passivating oxide layers is presently incomplete.
During the present …
Effect Of Silicon Content On The Corrosion Resistance And Radiation- Induced Embrittlement Of Materials For Advanced Heavy Liquid Metal Nuclear Systems, Ajit K. Roy
Transmutation Sciences Materials (TRP)
This task is focused on the evaluation of the effects of silicon content on both the corrosion behavior and radiation-induced embrittlement of martensitic stainless steels having compositions similar to that of modified 9Cr-1Mo steel, also known as T91 grade steel. T91 grade steel was selected to be a candidate structural material to contain molten lead-bismuth eutectic (LBE), which can act both as a target material and a coolant during the spallation process. The operating temperature during this process may range from 420-550 °C. Thus, moderate tensile strength of the containment material (T91) is a major requirement.
The beneficial effects of …
Theoretical Modeling Of Protective Oxide Layer Growth In Non-Isothermal Lead Alloy Coolant Systems, Yitung Chen, Jinsuo Zhang, Jichun Li
Theoretical Modeling Of Protective Oxide Layer Growth In Non-Isothermal Lead Alloy Coolant Systems, Yitung Chen, Jinsuo Zhang, Jichun Li
Transmutation Sciences Materials (TRP)
The goal of the proposed research project is to provide basic understanding of the protective oxide layer behaviors and to develop oxide layer growth models of steels in non-isothermal lead-alloys (lead or lead-bismuth eutectic) coolant systems. Precise studies and simulations of all hydrodynamics with thermal conditions encountered in practical coolant loop systems by use of different flowing conditions in the laboratory are difficult and expensive, if not impossible. Therefore it is important and necessary to develop theoretical models to predict the protective oxide layer behaviors at the design stage of a practical lead-alloy coolant system, to properly interpret and apply …
Development Of Nanostructure Based Corrosion-Barrier Coatings On Steel For Transmutation Applications, Biswajit Das
Development Of Nanostructure Based Corrosion-Barrier Coatings On Steel For Transmutation Applications, Biswajit Das
Transmutation Sciences Materials (TRP)
Advanced transmutation systems require structural materials that are able to withstand high neutron fluxes, high thermal cycling, and high resistance to chemical corrosion. The current candidate materials for such structures are ferritic and ferritic-martensitic steels due to their strong resistance to swelling, good microstructural stability under irradiation, and the retention of adequate ductility at typical reactor operating temperatures.
In parallel, lead-bismuth eutectic (LBE) has emerged as a potential spallation target material for efficient production of neutrons, as well as a coolant in the accelerator system. While LBE has excellent properties as a nuclear coolant, it is also highly corrosive to …
Development Of Integrated Process Simulation System Model For Spent Fuel Treatment Facility (Sftf) Design, Yitung Chen, Sean Hsieh
Development Of Integrated Process Simulation System Model For Spent Fuel Treatment Facility (Sftf) Design, Yitung Chen, Sean Hsieh
Separations Campaign (TRP)
The major objectives will lead to a creation of framework that combines all the strengths of AMUSE’s complicated calculations, well-established commercial system process package and ISOPro’s flexible parameter optimization modules. Development of the process simulation code can be done using the solvent extraction process at Argonne National Laboratory in collaboration with the research team from Mechanical Engineering Department at UNLV.
Research accomplishments:
- Integrated the ASPEN-Plus process model with the ISOPro system engineering modeling package, developed by the UNLV team.
- Tested the simplified system process integration using the ISOPro package.
- Generated complete version of the ISOPro package user manual and tutorial. …
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.
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 …
Design Concepts And Process Analysis For Transmuter Fuel Manufacturing, Georg F. Mauer
Design Concepts And Process Analysis For Transmuter Fuel Manufacturing, Georg F. Mauer
Fuels Campaign (TRP)
The safe and effective manufacturing of actinide-bearing fuels for any transmutation strategy requires that the entire manufacturing process be contained within a shielded hot cell environment. To ensure that the fabrication process is feasible, the entire process must be designed for remote operation. The equipment must be reliable enough to perform over several decades, and also easy to maintain or repair remotely. The facility must also be designed to facilitate its own decontamination and decommissioning. In addition to these design factors, the potential viability of any fuel fabrication process will also be impacted by a number of variables, such as …
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 …
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. …
Equivalent Circuit For Transient Conduction And Convection Systems, Bassam Sabry Mohammad Abdelnabi
Equivalent Circuit For Transient Conduction And Convection Systems, Bassam Sabry Mohammad Abdelnabi
Masters Theses
"Transient response of a natural convection system is investigated by numerical simulation using FLUENT code. An Integrator Circuit analogy was recently proposed for natural convection system. The proposed analogy was further confirmed by these recent simulations. New simulation results also suggest that a natural convection system acts as a "Low Pass" filter for transients. Transient transmission/attenuation factor was found to be a function of both fluid properties and the flow characteristics. Transmission/attenuation factor was also found to be a strong function of fluctuation frequency"--Abstract, page iv.
Interaction Between Metal Fission Products And Triso Coating Materials, Clemens Heske
Interaction Between Metal Fission Products And Triso Coating Materials, Clemens Heske
Fuels Campaign (TRP)
This project focuses on the chemical bonding and interface formation of metal fission products with the coating materials used in tri-isotropic (TRISO) fuel particles for gas-cooled reactors. By combining surface- and bulk-sensitive spectroscopic methods, intermediate chemical phases at the interface, intermixing/ diffusion behavior, and the electronic interface structure as a function of material (metal and coating materials) and temperature are examined.
In the past year, emphasis was placed on a detailed analysis and description of the Cs/SiC interface formation process.
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 …