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Artificial Intelligence and Machine Learning In Consumer Products

Description: This report provides background information on artificial intelligence and machine learning (AI/ML) and outlines a proposed framework to evaluate the safety of these technologies in consumer products. It outlines efforts underway and recommended future actions the CPSC can take to identify safety concerns with AI/ML technologies.
Date: May 19, 2021
Creator: Consumer Product Safety Commission (U.S.)
Partner: UNT Libraries Government Documents Department
open access

Artificial Intelligence: Background, Selected Issues, and Policy Considerations

Description: Report containing an overview of artificial intelligence (AI), recent growth in the field of AI, federal activity in AI (i.e., Executive Branch and Congress), and selected issues for congressional consideration to assist Congress in its work on AI.
Date: May 19, 2021
Creator: Harris, Laurie A.
Partner: UNT Libraries Government Documents Department
open access

Determination of Thickness of Oxide Film on Phosphor Bronze

Description: The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between these two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of the film, and surface area of film. A value of 1080 A was calculated as the thicknes… more
Date: May 19, 1959
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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Operation of the HRT Mockup with Boiling Fuel in a Titanium Pressurizer, Run CS-23

Description: The 0.045m UO2SO4, 0.036m CuSO4, 0.025 m H2SO4 solution (HRT fuel composition) was chemically stable during 1, 866hr of operation at 280ºC and 1500 psi. The system was pressurized by boiling a 0.4 gpm stream of the fuel in a titanium heat exchanger at 313ºC.
Date: May 19, 1959
Creator: Korsmeyer, R. B. & Harley, P. H.
Partner: UNT Libraries Government Documents Department
open access

Quarterly Report Technology of Non-Production Reactor Fuels Processing Budget Activity 2790

Description: This report summarizes the research and development work carried out during December, 1959, and January and February, 1960, for Budget Activity 2790 - Separations Development for Non-Production Reactors. The major effort on Activity 2790 has been completed. Current efforts on the remaining problem areas will enable Hanford to begin reprocessing fuel elements from power reactors which employ depleted or slightly enriched uranium fuels in July, 1962.
Date: May 19, 1960
Creator: Cooper, V. R.
Partner: UNT Libraries Government Documents Department
open access

Fission Project Yield of Inert Gases

Description: The final percentage of xenon created by fission in uranium and plutonium is a function of the neutron flux intensity. The flux dependence results because axenon 133 and 135 can be converted to a a stable xenon isotope by neutron capture instead of decaying into cesium.
Date: May 19, 1959
Creator: Merckx, K. R.
Partner: UNT Libraries Government Documents Department
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Full Scale 48 MC Cavity For Sparking Tests of Gaps Corresponding to 0.45 To 4.5 Mev Beam Energy

Description: It is proposed to test gaps corresponding to deuteron energies in the range of 0.45 to 4.5 Mev. The accelerator to be modeled is a 48 mc/sec cylindrical cavity in the TM010 mode with [formula] repeat length, [formula] gap, 0.25 megavolt per cavity foot peak r.f. gradient and strong focusing magnets alternating polarity at each drift tube.
Date: May 19, 1953
Creator: Unnam, Craig S.
Partner: UNT Libraries Government Documents Department
open access

Silicon Nitride As A High-Temperature Radome Material

Description: LRL has the responsibility of demonstrating the feasibility of a reactor for use as a power plant for a low-altitude, high-Mach-number missile. This reactor is literally a very high power air heater which must work at temperatures in excess of 2000' F. The reactor is exposed to high loads so one of the primary problems is providing high temperature structure. Considerable effort has been devoted to developing ceramic structural elements. One of the materials considered for this purpose is silic… more
Date: May 19, 1964
Creator: Wells, William M.
Partner: UNT Libraries Government Documents Department
open access

A Study of the Fabrication Failures for Zirconium and Zircaloy-2 Process Tubes and of the Annealing and Cold Rolling of Zircaloy-2

Description: A study of the fabrication failures for zirconium and zircaloy-2 process tubes was made. In the tube reducing operation, a non-uniform reduction in area for the cross section was found to be a major cause of failure. In annealing studies, a cycle of 2 hours at 820 deg C in vacuum followed by furnace cooling produced the greatest ductility of extruded zircaloy-2 for the annealing treatments studied. The ductility of cold worked and annealed zircaloy-2 was found to be superior to that of extruded… more
Date: May 19, 1955
Creator: Johnson, Dale E.
Partner: UNT Libraries Government Documents Department
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[Strategic planning grant proposal, May 19, 1993]

Description: A strategic planning grant proposal, submitted to the Getty Center for Education in the Arts, by D. Jack Davis and R. William McCarter. Attachments include a list of participants in different committees.
Date: May 19, 1993
Creator: Davis, D. Jack & McCarter, R. William
Partner: UNT Libraries Special Collections
open access

Weldability of Hayes Alloy #25

Description: Technical report describing the process to determine the fusion welding characteristics of Haynes Alloy #25 as applied to TLJ-100530, Corrosion Loops. Hayes Stellite Alloy #25 is a cobalt-base alloy for corrosion resistant high temperature applications. This material, when welded by the inert gas shielded tungsten arc method, produces sound ductile joints. Material thicknesses greater than 12 gauge require standard joint preparations, a V joint being preferred up to 1/4 inch and a U joint for … more
Date: May 19, 1959
Creator: Rogers, S. L.
Partner: UNT Libraries Government Documents Department
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NADAC and MERGE: computer codes for processing neutron activation analysis data

Description: Absolute disintegration rates of specific radioactive products induced by neutron irradition of a sample are determined by spectrometric analysis of gamma-ray emissions. Nuclide identification and quantification is carried out by a complex computer code GAMANAL (described elsewhere). The output of GAMANAL is processed by NADAC, a computer code that converts the data on observed distintegration rates to data on the elemental composition of the original sample. Computations by NADAC are on an abs… more
Date: May 19, 1977
Creator: Heft, Robert E. & Martin, Walton E.
Partner: UNT Libraries Government Documents Department
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Characterization of the uranium--2 weight percent molybdenum alloy. [Treatment to obtain 930 MPa yield strength (0. 2 percent)]

Description: The uranium-2 wt percent molybdenum alloy was prepared, processed, and age hardened to meet a minimum 930-MPa yield strength (0.2 percent) with a minimum of 10 percent elongation. These mechanical properties were obtained with a carbon level up to 300 ppM in the alloy. The tensile-test ductility is lowered by the humidity of the laboratory atmosphere. (auth)
Date: May 19, 1976
Creator: Hemperly, V. C.
Partner: UNT Libraries Government Documents Department
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Transient analysis isotope Brayton flight system

Description: Results of a study of the transient performance of the Isotope Brayton Flight System (IBFS) are presented.
Date: May 19, 1975
Partner: UNT Libraries Government Documents Department
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Investigation of the Electronic Structure of Solid Density Plasmas by X-Ray Scattering

Description: We present an improved analytical expression for the x-ray dynamic structure factor from a dense plasma which includes the effects of weakly bound electrons. This result can be applied to describe scattering from low to moderate Z plasmas, and it covers the entire range of plasma conditions that can be found in inertial confinement fusion experiments, from ideal to degenerate up to moderately coupled systems. We use our theory to interpret x-ray scattering experiments from solid density carbon … more
Date: May 19, 2003
Creator: Gregori, G; Glenzer, S H; Forest, F J; Kuhlbrodt, S; Redmer, R; Faussurier, G et al.
Partner: UNT Libraries Government Documents Department
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Flooding and mass transfer in Goodloe-packed columns. [For Kr absorption in liquid CO/sub 2/ in HTGR off-gas systems]

Description: Flooding and mass transfer experiments were performed with a CO/sub 2/-air/water system to examine mass transfer characteristics in Goodloe-packed columns of 6.4 and 15.2-cm ID for removal of radioactive Kr from HTGR off-gas. The flooding experiments verified previous correlations for the packing. The plug flow model was selected for calculation of the overall mass transfer coefficient, K/sub L/a. The correlation for K/sub L/a in terms of the molar liquid flow rate, L', is K/sub L/a = 0.359(L')… more
Date: May 19, 1976
Creator: Chao, E. I.; Bertolami, R. J.; Varlet, J. L. P. & Wilkes, G. R.
Partner: UNT Libraries Government Documents Department
open access

Hanford Site Climatological Data Summary 2003 with Historical Data

Description: This document presents the climatological data measured at the U.S. Department of Energy’s Hanford Site for calendar year 2003.
Date: May 19, 2004
Creator: Hoitink, Dana J.; Burk, Kenneth W.; Ramsdell, James V. & Shaw, William J.
Partner: UNT Libraries Government Documents Department
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Losses associated with the interim purification processing of neptunium

Description: This report discusses the interim program for the production of neptunium oxide at HAPO which applies the following processing steps: isolation of neptunium from the Purex process streams, using Purex flow sheets specially adapted for this purpose; purification of the neptunium nitrate by an ion exchange process carried out in one of the Redox laboratory (222-S) multi-curie cells; and precipitation of neptunium oxalate and conversion of the oxalate to oxide in laboratory-type equipment. The pro… more
Date: May 19, 1959
Creator: Harmon, K. M.
Partner: UNT Libraries Government Documents Department
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Compliance review for the UNH Storage Tank

Description: The purpose of Project S-4257, USF-UNH 150,000 Gallon Storage Tank, is to provide interim storage for the liquid uranyl nitrate (UNH) product from H-Canyon until the UNH can be processed in the new Uranium Solidification Facility (Project S-2052). NPSR was requested by Project Management and DOE-SR to perform a design compliance review for the UNH Storage Tank to support the Operational Readiness Review (ORR) and the Operational Readiness Evaluation (ORE), respectively. The project was reviewed… more
Date: May 19, 1992
Creator: Low, J. M.
Partner: UNT Libraries Government Documents Department
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Hanford Radiological Protection Support Services Annual Report:1999

Description: Radiation protection services performed routinely by Pacific Northwest National Laboratory for the U.S. Department of Energy Richland Operations Office and Hanford Site contractors are summarized in this annual report for 1999. It addresses services and special studies or investigations provided by the primary projects managed under the Radiation and Health Technology group, including external dosimetry, internal dosimetry, whole body counting, radiation records, instrumentation services and te… more
Date: May 19, 2000
Creator: Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A. & Piper, Roman K.
Partner: UNT Libraries Government Documents Department
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The development of a generic ecosystem model for assessing the effects of elevated carbon dioxide on ecosystems. Progress report, September 1, 1986--May 18, 1987

Description: This report consists of three major sections which are: progress made on the development of a generic plant growth model, progress made on the holistic ecosystem model, and a summary outlining future directions of our modeling efforts. The major accomplishments of the plant growth modeling have been the identification and implementation of components for the photosynthesis module, development of a plant canopy module, and further refinement of the various modules that make up the basic structur… more
Date: May 19, 1987
Creator: Reynolds, J. F.; Skiles, J. W. & Dougherty, R. L.
Partner: UNT Libraries Government Documents Department
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