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319,268 Matching Results
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Beam-dump Kicker Magnets
None
Date:
March 4, 2014
Creator:
Bulos, Fatin; Odian, A. & Tomlin, Bill T.
Object Type:
Report
System:
The UNT Digital Library
Damping Ring Kickers
None
Date:
March 4, 2014
Creator:
Bulos, F.; Tomlin, Bill T. & Weaver, J.
Object Type:
Report
System:
The UNT Digital Library
Dry Cask Storage Inspection and Monitoring. Interim Report.
None
Date:
March 4, 2014
Creator:
Bakhtiari, S.; Elmer, T. W.; Koehl, E. R.; Wang, K.; Raptis, A. C.; Kunerth, D. C. et al.
Object Type:
Report
System:
The UNT Digital Library
A Framework for Adaptable Operating and Runtime Systems
The emergence of new classes of HPC systems where performance improvement is enabled by Moore’s Law for technology is manifest through multi-core-based architectures including specialized GPU structures. Operating systems were originally designed for control of uniprocessor systems. By the 1980s multiprogramming, virtual memory, and network interconnection were integral services incorporated as part of most modern computers. HPC operating systems were primarily derivatives of the Unix model with Linux dominating the Top-500 list. The use of Linux for commodity clusters was first pioneered by the NASA Beowulf Project. However, the rapid increase in number of cores to achieve performance gain through technology advances has exposed the limitations of POSIX general-purpose operating systems in scaling and efficiency. This project was undertaken through the leadership of Sandia National Laboratories and in partnership of the University of New Mexico to investigate the alternative of composable lightweight kernels on scalable HPC architectures to achieve superior performance for a wide range of applications. The use of composable operating systems is intended to provide a minimalist set of services specifically required by a given application to preclude overheads and operational uncertainties (“OS noise”) that have been demonstrated to degrade efficiency and operational consistency. This project was undertaken …
Date:
March 4, 2014
Creator:
Sterling, Thomas
Object Type:
Report
System:
The UNT Digital Library
Kicker Magnet and Pulser
None
Date:
March 4, 2014
Creator:
Bulos, Fatin
Object Type:
Report
System:
The UNT Digital Library
Parasitic Mode Losses in the Damping Ring
None
Date:
March 4, 2014
Creator:
Wilson, Perry B.
Object Type:
Report
System:
The UNT Digital Library
Modified Anti-de-Sitter Metric, Light-Front Quantized QCD, and Conformal Quantum Mechanics
None
Date:
March 3, 2014
Creator:
Dosch, Hans Gunter; Brodsky, Stanley J. & de Teramond, Guy F.
Object Type:
Article
System:
The UNT Digital Library
Representative Atmospheric Plume Development for Elevated Releases
An atmospheric explosion of a low-yield nuclear device will produce a large number of radioactive isotopes, some of which can be measured with airborne detection systems. However, properly equipped aircraft may not arrive in the region where an explosion occurred for a number of hours after the event. Atmospheric conditions will have caused the radioactive plume to move and diffuse before the aircraft arrives. The science behind predicting atmospheric plume movement has advanced enough that the location of the maximum concentrations in the plume can be determined reasonably accurately in real time, or near real time. Given the assumption that an aircraft can follow a plume, this study addresses the amount of atmospheric dilution expected to occur in a representative plume as a function of time past the release event. The approach models atmospheric transport of hypothetical releases from a single location for every day in a year using the publically available HYSPLIT code. The effective dilution factors for the point of maximum concentration in an elevated plume based on a release of a non-decaying, non-depositing tracer can vary by orders of magnitude depending on the day of the release, even for the same number of hours after the release …
Date:
March 3, 2014
Creator:
Eslinger, Paul W.; Lowrey, Justin D.; McIntyre, Justin I.; Miley, Harry S. & Prichard, Andrew W.
Object Type:
Report
System:
The UNT Digital Library
Sample Results From The Extraction, Scrub, And Strip Test For The Blended NGS Solvent
This report summarizes the results of the extraction, scrub, and strip testing for the September 2013 sampling of the Next Generation Solvent (NGS) Blended solvent from the Modular Caustic Side-Solvent Extraction Unit (MCU) Solvent Hold Tank. MCU is in the process of transitioning from the BOBCalixC6 solvent to the NGS Blend solvent. As part of that transition, MCU has intentionally created a blended solvent to be processed using the Salt Batch program. This sample represents the first sample received from that blended solvent. There were two ESS tests performed where NGS blended solvent performance was assessed using either the Tank 21 material utilized in the Salt Batch 7 analyses or a simulant waste material used in the V-5/V-10 contactor testing. This report tabulates the temperature corrected cesium distribution, or DCs values, step recovery percentage, and actual temperatures recorded during the experiment. This report also identifies the sample receipt date, preparation method, and analysis performed in the accumulation of the listed values. The calculated extraction DCs values using the Tank 21H material and simulant are 59.4 and 53.8, respectively. The DCs values for two scrub and three strip processes for the Tank 21 material are 4.58, 2.91, 0.00184, 0.0252, and 0.00575, …
Date:
March 3, 2014
Creator:
Washington, A. L. II & Peters, T. B.
Object Type:
Report
System:
The UNT Digital Library
Case Study: Mobile Photovoltaic System at Bechler Meadows Ranger Station, Yellowstone National Park (Brochure)
The mobile PV/generator hybrid system deployed at Bechler Meadows provides a number of advantages. It reduces on-site air emissions from the generator. Batteries allow the generator to operate only at its rated power, reducing run-time and fuel consumption. Energy provided by the solar array reduces fuel consumption and run-time of the generator. The generator is off for most hours providing peace and quiet at the site. Maintenance trips from Mammoth Hot Springs to the remote site are reduced. The frequency of intrusive fuel deliveries to the pristine site is reduced. And the system gives rangers a chance to interpret Green Park values to the visiting public. As an added bonus, the system provides all these benefits at a lower cost than the basecase of using only a propane-fueled generator, reducing life cycle cost by about 26%.
Date:
March 1, 2014
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Developing Spent Fuel Assembly for Advanced NDA Instrument Calibration - NGSI Spent Fuel Project
None
Date:
March 1, 2014
Creator:
Hu, Jianwei; Gauld, Ian C; Banfield, James & Skutnik, Steven
Object Type:
Report
System:
The UNT Digital Library
The Effect of Heat Treatments and Coatings on the Outgassing Rate of Stainless Steel Chambers
The outgassing rates of four nominally identical 304L stainless steel vacuum chambers were measured to determine the effect of chamber coatings and heat treatments. One chamber was coated with titanium nitride (TiN) and one with amorphous silicon (a-Si) immediately following fabrication. One chamber remained uncoated throughout, and the last chamber was first tested without any coating, and then coated with a-Si following a series of heat treatments. The outgassing rate of each chamber was measured at room temperatures between 15 and 30 deg C following bakes at temperatures between 90 and 400 deg C. Measurements for bare steel showed a significant reduction in the outgassing rate by more than a factor of 20 after a 400 deg C heat treatment (3.5 x 10{sup 12} TorrL s{sup -1}cm{sup -2} prior to heat treatment, reduced to 1.7 x 10{ sup -13} TorrL s{sup -1}cm{sup -2} following heat treatment). The chambers that were coated with a-Si showed minimal change in outgassing rates with heat treatment, though an outgassing rate reduced by heat treatments prior to a-Si coating was successfully preserved throughout a series of bakes. The TiN coated chamber exhibited remarkably low outgassing rates, up to four orders of magnitude lower than the …
Date:
March 1, 2014
Creator:
Mamum, Md Abdullah A.; Elmustafa, Abdelmageed A,; Stutzman, Marcy L.; Adderley, Philip A. & Poelker, Matthew
Object Type:
Article
System:
The UNT Digital Library
Energy Savings and Peak Demand Reduction of a SEER 21 Heat Pump vs. a SEER 13 Heat Pump with Attic and Indoor Duct Systems
This report describes results of experiments that were conducted in an unoccupied 1600 square foot house--the Manufactured Housing (MH Lab) at the Florida Solar Energy Center (FSEC)--to evaluate the delivered performance as well as the relative performance of a SEER 21 variable capacity heat pump versus a SEER 13 heat pump. The performance was evaluated with two different duct systems: a standard attic duct system and an indoor duct system located in a dropped-ceiling space.
Date:
March 1, 2014
Creator:
Cummings, J. & Withers, C.
Object Type:
Report
System:
The UNT Digital Library
HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORE 4: RANDOM PACKING WITH A 1:1 MODERATOR-TO-FUEL PEBBLE RATIO
In its deployment as a pebble bed reactor (PBR) critical facility from 1992 to 1996, the PROTEUS facility was designated as HTR-PROTEUS. This experimental program was performed as part of an International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) on the Validation of Safety Related Physics Calculations for Low Enriched HTGRs. Within this project, critical experiments were conducted for graphite moderated LEU systems to determine core reactivity, flux and power profiles, reaction-rate ratios, the worth of control rods, both in-core and reflector based, the worth of burnable poisons, kinetic parameters, and the effects of moisture ingress on these parameters. One benchmark experiment was evaluated in this report: Core 4. Core 4 represents the only configuration with random pebble packing in the HTR-PROTEUS series of experiments, and has a moderator-to-fuel pebble ratio of 1:1. Three random configurations were performed. The initial configuration, Core 4.1, was rejected because the method for pebble loading, separate delivery tubes for the moderator and fuel pebbles, may not have been completely random; this core loading was rejected by the experimenters. Cores 4.2 and 4.3 were loaded using a single delivery tube, eliminating the possibility for systematic ordering effects. The second and third cores differed slightly …
Date:
March 1, 2014
Creator:
Bess, John D. & Montierth, Leland M.
Object Type:
Report
System:
The UNT Digital Library
HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORES 9 & 10: COLUMNAR HEXAGONAL POINT-ON-POINT PACKING WITH A 1:1 MODERATOR-TO-FUEL PEBBLE RATIO
PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PROTEUS. The nomenclature was used to indicate that this series consisted of High Temperature Reactor experiments performed in the PROTEUS assembly. During this period, seventeen critical configurations were assembled and various reactor physics experiments were conducted. These experiments included measurements of criticality, differential and integral control rod and safety rod worths, kinetics, reaction rates, water ingress effects, and small sample reactivity effects (Ref. 3). HTR-PROTEUS was constructed, and the experimental program was conducted, for the purpose of providing experimental benchmark data for assessment of reactor physics computer codes. Considerable effort was devoted to benchmark calculations as a part of the HTR-PROTEUS program. References 1 and 2 provide detailed data for use in constructing models for codes to be assessed. Reference 3 is a comprehensive summary of …
Date:
March 1, 2014
Creator:
Bess, John D.
Object Type:
Report
System:
The UNT Digital Library
NEUTRON RADIOGRAPHY (NRAD) REACTOR 64-ELEMENT CORE UPGRADE
The neutron radiography (NRAD) reactor is a 250 kW TRIGA (registered) (Training, Research, Isotopes, General Atomics) Mark II , tank-type research reactor currently located in the basement, below the main hot cell, of the Hot Fuel Examination Facility (HFEF) at the Idaho National Laboratory (INL). It is equipped with two beam tubes with separate radiography stations for the performance of neutron radiography irradiation on small test components. The interim critical configuration developed during the core upgrade, which contains only 62 fuel elements, has been evaluated as an acceptable benchmark experiment. The final 64-fuel-element operational core configuration of the NRAD LEU TRIGA reactor has also been evaluated as an acceptable benchmark experiment. Calculated eigenvalues differ significantly (approximately +/-1%) from the benchmark eigenvalue and have demonstrated sensitivity to the thermal scattering treatment of hydrogen in the U-Er-Zr-H fuel.
Date:
March 1, 2014
Creator:
Bess, John D.
Object Type:
Report
System:
The UNT Digital Library
Understanding Mechanisms of Radiological Contamination
Over the last 50 years, the study of radiological contamination and decontamination has expanded significantly. This paper addresses the mechanisms of radiological contamination that have been reported and then discusses which methods have recently been used during performance testing of several different decontamination technologies. About twenty years ago the Idaho Nuclear Technology Engineering Center (INTEC) at the INL began a search for decontamination processes which could minimize secondary waste. In order to test the effectiveness of these decontamination technologies, a new simulated contamination, termed SIMCON, was developed. SIMCON was designed to replicate the types of contamination found on stainless steel, spent fuel processing equipment. Ten years later, the INL began research into methods for simulating urban contamination resulting from a radiological dispersal device (RDD). This work was sponsored by the Defense Advanced Research Projects Agency (DARPA) and included the initial development an aqueous application of contaminant to substrate. Since 2007, research sponsored by the US Environmental Protection Agency (EPA) has advanced that effort and led to the development of a contamination method that simulates particulate fallout from an Improvised Nuclear Device (IND). The IND method diverges from previous efforts to create tenacious contamination by simulating a reproducible “loose” contamination. Examining …
Date:
March 1, 2014
Creator:
Demmer, Rick; Drake, John & Ryan James, PhD
Object Type:
Article
System:
The UNT Digital Library
US DOE-EM On-Site Disposal Cell Working Group - Fostering Communication On Performance Assessment Challenges
On-site disposal cells are in use and being considered at several U.S. Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These facilities are typically developed with regulatory oversight from States and/or the US Environmental Protection Agency (USEPA) in addition to USDOE. The facilities are developed to meet design standards for disposal of hazardous waste as well as the USDOE performance based standards for disposal of radioactive waste. The involvement of multiple and different regulators for facilities across separate sites has resulted in some differences in expectations for performance assessments and risk assessments (PA/RA) that are developed for the disposal facilities. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. The working group holds teleconferences, as needed, focusing on specific topics of interest. The topics addressed to date include an assessment of the …
Date:
March 1, 2014
Creator:
Seitz, Roger R.; Suttora, Linda C. & Phifer, Mark
Object Type:
Article
System:
The UNT Digital Library
Cast Stone Formulation At Higher Sodium Concentrations
A low temperature waste form known as Cast Stone is being considered to provide supplemental Low Activity Waste (LAW) immobilization capacity for the Hanford site. Formulation of Cast Stone at high sodium concentrations is of interest since a significant reduction in the necessary volume of Cast Stone and subsequent disposal costs could be achieved if an acceptable waste form can be produced with a high sodium molarity salt solution combined with a high water to premix (or dry blend) ratio. The objectives of this study were to evaluate the factors involved with increasing the sodium concentration in Cast Stone, including production and performance properties and the retention and release of specific components of interest. Three factors were identified for the experimental matrix: the concentration of sodium in the simulated salt solution, the water to premix ratio, and the blast furnace slag portion of the premix. The salt solution simulants used in this study were formulated to represent the overall average waste composition. The cement, blast furnace slag, and fly ash were sourced from a supplier in the Hanford area in order to be representative. The test mixes were prepared in the laboratory and fresh properties were measured. Fresh density increased …
Date:
February 28, 2014
Creator:
Fox, K. M.; Roberts, K. A. & Edwards, T. B.
Object Type:
Report
System:
The UNT Digital Library
Center for Momentum Transport and Flow Organization in Plasmas and Magnetofluids (CMTFO)
The CMTFO funding partially supports a junior researcher and a graduate student at UCI. During this project, we have further developed the global gyrokinetic particle code GTC to study the momentum transport in tokamak driven by electrostatic ion temperature gradient (ITG) turbulence [1] with kinetic electrons and by collisionless trapped electron mode (CTEM) turbulence [2]. We have also upgraded GTC for fully electromagnetic simulation and for linear plasma configuration with verification and validation of the electron temperature gradient (ETG) turbulence in Columbia Linear Machine. The followings are the highlights on the physics results reported in the key publications of this project.
Date:
February 28, 2014
Creator:
Lin, Zhihong
Object Type:
Report
System:
The UNT Digital Library
Multi-Hybrid Power Vehicles with Cost Effective and Durable Polymer Electrolyte
Anima Bose, the principal investigator of the project, originally proposed to develop composite membranes to operate PEMFCs at much higher temperatures than 80{degrees}C and to alleviate the flooding problems often encountered in Nafion menmbrane containing fuel cells. The PI has successfully created composite membranes by blending small quantities of octasilane-poss (OSP) with Nafion. The composite membranes exhibited temperature tolerance up to 110{degrees}C without scarifying cell performance as determined by polarization curves and proton conductivity measurements. These membranes also exhibited superior water management performance as evident from the lack of flooding. Furthermore, these fuel cells performed well under reduced humidities. Structural and thermal analyses revealed that these Nafion-octasilane composite membranes are homogenous at concentrations up to 3 wt% of the OSP and that the siloxane offers additional thermal stability.
Date:
February 28, 2014
Creator:
Bose, Anima
Object Type:
Report
System:
The UNT Digital Library
Reversal of OFI and CHF in Research Reactors Operating at 1 to 50 Bar. Version 1.0
None
Date:
February 28, 2014
Creator:
Kalimullah, M.; Olson, A. P.; Dionne, B.; Feldman, E. E. & Matos, J. E.
Object Type:
Report
System:
The UNT Digital Library
Shallow Water Offshore Wind Optimization for the Great Lakes (DE-FOA-0000415) Final Report: A Conceptual Design for Wind Energy in the Great Lakes
The primary objective of the project was to develop a innovative Gravity Base Foundation (GBF) concepts, including fabrication yards, launching systems and installation equipment, for a 500MW utility scale project in the Great Lakes (Lake Erie). The goal was to lower the LCOE by 25%. The project was the first to investigate an offshore wind project in the Great Lakes and it has furthered the body of knowledge for foundations and installation methods within Lake Erie. The project collected historical geotechnical information for Lake Erie and also used recently obtained data from the LEEDCo Icebreaker Project (FOA DE-EE0005989) geotechnical program to develop the conceptual designs. Using these data-sets, the project developed design wind and wave conditions from actual buoy data in order to develop a concept that would de-risk a project using a GBF. These wind and wave conditions were then utilized to create reference designs for various foundations specific to installation in Lake Erie. A project partner on the project (Weeks Marine) provided input for construction and costing the GBF fabrication and installation. By having a marine contractor with experience with large marine projects as part of the team provides credibility to the LCOE developed by NREL. NREL then …
Date:
February 28, 2014
Creator:
Wissemann, Chris & White, Stanley M
Object Type:
Report
System:
The UNT Digital Library
Analysis Of Tank 38H (HTF-38-14-6, 7) And Tank 43H (HTF-43-14-8, 9) Samples For Support Of The Enrichment Control And Corrosion Control Programs
SRNL performed analysis on Tanks 38H and 43H surface and subsurface supernate samples to support ECP and CCP. The U-235 mass divided by the total U mass ranged from 0.0059 to 0.0060. Uranium concentration ranged from 53.1 mg/L in the Tank 43H surface sample to the 85.1 mg/L in the Tank 38H subsurface sample. The U-235/U and uranium concentration are in line with the prior 2H-Evaporator System ECP samples.
Date:
February 27, 2014
Creator:
Martino, C. J.
Object Type:
Report
System:
The UNT Digital Library