Latest content added for UNT Digital Library Partner: UNT Libraries Government Documents Departmenthttps://digital.library.unt.edu/explore/partners/UNTGD/browse/?start=503302018-11-03T11:47:27-05:00UNT LibrariesThis is a custom feed for browsing UNT Digital Library Partner: UNT Libraries Government Documents DepartmentProduction test IP-527-A effect of eccentricity on the irradiation behavior of KVNS fuel elements2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317946/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317946/"><img alt="Production test IP-527-A effect of eccentricity on the irradiation behavior of KVNS fuel elements" title="Production test IP-527-A effect of eccentricity on the irradiation behavior of KVNS fuel elements" src="https://digital.library.unt.edu/ark:/67531/metadc1317946/small/"/></a></p><p>The objectives of this production test are to confirm the KVNS fuel element design, determine the effect of support height on annulus coolant temperature distribution (R Value), evaluate the effect of eccentricity on KVNS fuel element irradiation behavior.</p>Development of a simple thermophysical property model for cane fiberboard packages subjected to a hypothetical accident fire2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317947/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317947/"><img alt="Development of a simple thermophysical property model for cane fiberboard packages subjected to a hypothetical accident fire" title="Development of a simple thermophysical property model for cane fiberboard packages subjected to a hypothetical accident fire" src="https://digital.library.unt.edu/ark:/67531/metadc1317947/small/"/></a></p><p>A simple thermophysical property model has been developed to analytically determine the thermal response of cane fiberboard when exposed to temperatures and heat fluxes associated with the hypothetical aident condition and the post fire cooling. The complete model was developed from high temperature cane fiberboard 1-D test results and consists of heating and cooling sub-models. The heating property model accounts for the enhanced heat transfer of the hot gases in the fiberboard, the loss of energy via venting, and the loss of mass from venting during the heating portion of the test. The cooling property model accounts for the degraded material effects and the continued heat transfer associated with the hot gases after removal of the external heating source. Agreement between the test results of a four inch thick fiberboard sample with the analytical application of the complete property model is quite good and will be presented.</p>An improved method for producing radiation hybrids applied to human chromosome 19. Technical progress report, March 1, 1991--February 28, 19922018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317948/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317948/"><img alt="An improved method for producing radiation hybrids applied to human chromosome 19. Technical progress report, March 1, 1991--February 28, 1992" title="An improved method for producing radiation hybrids applied to human chromosome 19. Technical progress report, March 1, 1991--February 28, 1992" src="https://digital.library.unt.edu/ark:/67531/metadc1317948/small/"/></a></p><p>At the initiation of the grant we had just produced radiation hybrids from a monochromosomal microcell hybrid containing human chromosome 19 as its only human component. Radiation hybrids were produced using doses of radiation ranging from 1000--8000 rads. Lethally irradiated cells were then fused to hamster recipients (CHTG49) and selected for growth in histidinol. Approximately 240 clones were isolated and 75 clones were expanded for the isolation of DNA. This report describes in situ hybridization studies and the introduction of markers into human chromosome 19.</p>Chemical Processing Division monthly report, October 19662018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317949/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317949/"><img alt="Chemical Processing Division monthly report, October 1966" title="Chemical Processing Division monthly report, October 1966" src="https://digital.library.unt.edu/ark:/67531/metadc1317949/small/"/></a></p><p>October performance of the plant production facilities was outstanding (915.2 tons U processed by Purex; 625.4 kg Pu separated by Redox/Purex). Redox processed three types of feed. Operation of incinerator furnace was resumed in Pu finishing processes. Capital cost estimates were prepared for several schemes for power reactor fuel reprocessing in Redox. Redox encased waste lines and line support system were found to be in good condition. H concentration in Redox dissolver off-gases occasionally exceeded lower flammable limits while sodium nitrate from high level waste storage tanks was used to suppress hydrogen.</p>Field demonstrations of passive detectors for screening of alpha contaminated soils2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317950/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317950/"><img alt="Field demonstrations of passive detectors for screening of alpha contaminated soils" title="Field demonstrations of passive detectors for screening of alpha contaminated soils" src="https://digital.library.unt.edu/ark:/67531/metadc1317950/small/"/></a></p><p>There are numerous sites around the country, DOE and otherwise, that are faced with the daunting task of remediating radiologically contaminated soils and groundwaters. Some of these sites, such as the Nevada Test Site and the Rocky Flats Plant, have contaminants that have been dispersed over wide areas. The costs of the characterization phase alone for such remediation programs can be prohibitive. Therefore there are pressing needs for testing and evaluation of new technologies for screening for radiological contaminants that may offer significant advantages in capital costs, ease of use, sensitivity, ruggedness, and/or reliability. This work reports on laboratory and Field tests of two types of passive alpha detectors, electret ionization chambers (EIC`s) and alpha track detectors (ATD`s), that have been commercially developed for indoor radon measurements. Previous work documented calibration and measurement protocols developed for these detectors for indoor surface contamination measurements.</p>User`s manual for SNL-SAND-II code2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317951/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317951/"><img alt="User`s manual for SNL-SAND-II code" title="User`s manual for SNL-SAND-II code" src="https://digital.library.unt.edu/ark:/67531/metadc1317951/small/"/></a></p><p>Sandia National Laboratories, in the process of characterizing the neutron environments at its reactor facilities, has developed an enhanced version of W. McElroy`s original SAND-II code. The enhanced input, output, and plotting interfaces make the code much easier to use. The basic physics and operation of the code remain unchanged. Important code enhancements include the interfaces to the latest ENDF/B-VI and IRDF-90 dosimetry-quality cross sections and the ability to use silicon displacement-sensitive devices as dosimetry sensors.</p>New techniques for positron emission tomography in the study of human neurological disorders2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317952/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317952/"><img alt="New techniques for positron emission tomography in the study of human neurological disorders" title="New techniques for positron emission tomography in the study of human neurological disorders" src="https://digital.library.unt.edu/ark:/67531/metadc1317952/small/"/></a></p><p>The general goals of the physics and kinetic modeling projects are to: (1) improve the quantitative information extractable from PET images, and (2) develop, implement and optimize tracer kinetic models for new PET neurotransmitter/receptor ligands aided by computer simulations. Work towards improving PET quantification has included projects evaluating: (1) iterative reconstruction algorithms using supplemental boundary information, (2) automated registration of dynamic PET emission and transmission data using sinogram edge detection, and (3) automated registration of multiple subjects to a common coordinate system, including the use of non-linear warping methods. Simulation routines have been developed providing more accurate representation of data generated from neurotransmitter/receptor studies. Routines consider data generated from complex compartmental models, high or low specific activity administrations, non-specific binding, pre- or post-injection of cold or competing ligands, temporal resolution of the data, and radiolabeled metabolites. Computer simulations and human PET studies have been performed to optimize kinetic models for four new neurotransmitter/receptor ligands, [{sup 11}C]TRB (muscarinic), [{sup 11}C]flumazenil (benzodiazepine), [{sup 18}F]GBR12909, (dopamine), and [{sup 11}C]NMPB (muscarinic).</p>[Research on shallow-shelf carbonate (Class 2) reservoirs]. Quarterly report, July--September 19922018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317953/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317953/"><img alt="[Research on shallow-shelf carbonate (Class 2) reservoirs]. Quarterly report, July--September 1992" title="[Research on shallow-shelf carbonate (Class 2) reservoirs]. Quarterly report, July--September 1992" src="https://digital.library.unt.edu/ark:/67531/metadc1317953/small/"/></a></p><p>The purpose of this contract is to provide technical and analytical support services for TORIS at BPO. The discussion of the work performed is organized by task order. The objective of task order 1 is to support the BPO TORIS Program Coordinator in the maintenance, operations, enhancement, and applications of the data bases, models, and hardware of TORIS on the BPO computer. Objective of task order 2 is to support BPO management in following: analyzing, interpreting, and reporting on trends in the oil and gas industry; and technical assistance in the areas of environmental health and safety and quality control for quality assurance procedures. Accomplishments for this quarter are described.</p>Exotic Atoms. Technical Progress Report, February 1, 1992--January 31, 19932018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317954/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317954/"><img alt="Exotic Atoms. Technical Progress Report, February 1, 1992--January 31, 1993" title="Exotic Atoms. Technical Progress Report, February 1, 1992--January 31, 1993" src="https://digital.library.unt.edu/ark:/67531/metadc1317954/small/"/></a></p><p>The experiments use a solid hydrogen layer to form muonic hydrogen isotopes that escape into vacuum. The method relies on transfer of the muon from protium to either a deuteron or a triton. The resulting muonic deuterium or muonic tritium will not immediately thermalize because of the very low elastic cross sections, and may be emitted from the surface of the layer. Measurements which detect decay electrons, muonic x-rays, and fusion products have been used to study the processes. A target has been constructed which exploits muonic atom emission in order to learn more about the energy dependence of transfer and muon molecular formation.</p>Ionic properties of hydrogenated and fluorinated fullerenes2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317955/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317955/"><img alt="Ionic properties of hydrogenated and fluorinated fullerenes" title="Ionic properties of hydrogenated and fluorinated fullerenes" src="https://digital.library.unt.edu/ark:/67531/metadc1317955/small/"/></a></p><p>Using mass spectrometry, the ionization potentials (IP) of C{sub 60}H{sub n} for even-numbered n=2-12 were determined to be 6.75-7.5 eV, and for odd-numbered n were below 6.75 eV (for C{sub 60}, IP is 7.65 eV). Electron affinities (EA) of these species rapidly decrease with increasing n. IPs and EAs for C{sub 60}F{sub x}, on the other hand, both increase dramatically upon fluorination. A second electron can be added to gaseous C{sub 60}F{sub 48}{sup {minus}}; the resulting doubly charged anion is more stable than the singly charged anion.</p>Advances in rapid prototyping2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317956/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317956/"><img alt="Advances in rapid prototyping" title="Advances in rapid prototyping" src="https://digital.library.unt.edu/ark:/67531/metadc1317956/small/"/></a></p><p>Recent advances in stereolithography and selective laser sintering have had a significant impact on the overall quality of parts produced using these rapid prototyping processes. The development and implementation of 3D System`s QuickCast{trademark} resin and software for building investment casting patterns have proven to be major steps toward fabricating highly accurate patterns with very good surface finishes. Sandia uses patterns generated from rapid prototyping processes to reduce the cycle time and cost of fabricating prototype parts in support of a Sandia National Laboratories managed program called FASTCAST. As participants in the Beta test program for QuickCast{trademark} resin and software, they experienced a steep learning curve and were able to build accurate parts in a short period of time. It is now possible, using this technology, to produce highly accurate prototype parts as well as acceptable firs article and small lots size production parts. They use the Selective Laser Sintering (SLS) process to fabricate prototype wax patterns for investment casting. DTM Corporation recently introduced the use of their polycarbonate material for fabricating investment casting patterns. The polycarbonate material is processed significantly faster, with improved strength, dimensional stability, and without a support structure during the build process. Sandia is currently changing from investment casting wax to polycarbonate for the fabrication of investment casting patterns using the SLS process. This presentation will focus on the successes with these new materials from the standpoints of application, accuracy, surface finish, and post processing. Also presented will be examples of parts manufactured by these processes.</p>Design of operator interfaces for ``bumpless`` transfers between operator behaviors2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317957/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317957/"><img alt="Design of operator interfaces for ``bumpless`` transfers between operator behaviors" title="Design of operator interfaces for ``bumpless`` transfers between operator behaviors" src="https://digital.library.unt.edu/ark:/67531/metadc1317957/small/"/></a></p><p>Advances in the science and art of man-machine interface design have taken major strides forward for interface design practitioners with the advent of the computer. one concern still extant, however, is the need for design of interfaces that minimize confusion when an operator is required to shift from the different levels of cognitive control of skill, rule, and knowledge-based behaviors, (e.g., if an operator is following a set of procedures and a procedural error is noted by the operator, the behavior may, of necessity, shift from rule-based to a knowledge-based behavior). Shifting of the cognitive control levels requires that the information to be displayed to the operator should be designed so that a ``bumpless`` transfer can be made between the behavioral modes, thus reducing the possibility of error. This paper introduces a way to design human interfaces so that skill, rule, and knowledge-based behaviors are supported and provides for the necessary interchanges between behavioral types.</p>Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 1, Methodology and results2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317883/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317883/"><img alt="Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 1, Methodology and results" title="Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 1, Methodology and results" src="https://digital.library.unt.edu/ark:/67531/metadc1317883/small/"/></a></p><p>This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste. Although numerous caveats must be placed on the results, the general findings were as follows: Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.</p>Knowledges and abilities catalog for nuclear power plant operators: Savannah River Site (SRS) production reactors2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317884/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317884/"><img alt="Knowledges and abilities catalog for nuclear power plant operators: Savannah River Site (SRS) production reactors" title="Knowledges and abilities catalog for nuclear power plant operators: Savannah River Site (SRS) production reactors" src="https://digital.library.unt.edu/ark:/67531/metadc1317884/small/"/></a></p><p>The Knowledges and Abilities Catalog for Nuclear Power Plant Operations: Savannah River Site (SRS) Production Reactors, provides the basis for the development of content-valid certification examinations for Senior Reactor Operators (SROs) and Central Control Room Supervisors (SUP). The position of Shift Technical Engineer (STE) has been included in the catalog for completeness. This new SRS reactor operating shift crew position is held by an individual holding a CCR Supervisor Certification who has received special engineering and technical training. Also, the STE has a Bachelor of Science degree in engineering or a related technical field. The SRS catalog contains approximately 2500 knowledge and ability (K/A) statements for SROs and SUPs at heavy water moderated production reactors. Each K/A statement has been rated for its importance to the safe operation of the plant in a manner ensuring the health and safety of the public. The SRS K/A catalog is presently organized into five major sections: Plant Systems grouped by Safety Function, Plant Wide Generic K/As, Emergency Plant Evolutions, Theory and Components (to be developed).</p>Geophysical data fusion for subsurface imaging. Phase 12018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317885/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317885/"><img alt="Geophysical data fusion for subsurface imaging. Phase 1" title="Geophysical data fusion for subsurface imaging. Phase 1" src="https://digital.library.unt.edu/ark:/67531/metadc1317885/small/"/></a></p><p>A geophysical data fusion methodology is under development to combine data from complementary geophysical sensors and incorporate geophysical understanding to obtain three dimensional images of the subsurface. The research reported here is the first phase of a three phase project. The project focuses on the characterization of thin clay lenses (aquitards) in a highly stratified sand and clay coastal geology to depths of up to 300 feet. The sensor suite used in this work includes time-domain electromagnetic induction (TDEM) and near surface seismic techniques. During this first phase of the project, enhancements to the acquisition and processing of TDEM data were studied, by use of simulated data, to assess improvements for the detection of thin clay layers. Secondly, studies were made of the use of compressional wave and shear wave seismic reflection data by using state-of-the-art high frequency vibrator technology. Finally, a newly developed processing technique, called ``data fusion,`` was implemented to process the geophysical data, and to incorporate a mathematical model of the subsurface strata. Examples are given of the results when applied to real seismic data collected at Hanford, WA, and for simulated data based on the geology of the Savannah River Site.</p>Supplementary E-N load conversion ratio data2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317886/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317886/"><img alt="Supplementary E-N load conversion ratio data" title="Supplementary E-N load conversion ratio data" src="https://digital.library.unt.edu/ark:/67531/metadc1317886/small/"/></a></p><p>The interim report included an analysis of those E-N case and blanket loading conversion ratio data which were available at that time, and an extrapolation of those data to expected, optimum, E-N operating conditions. Since issuance of the interim report further tritium yield data have become available from extraction of the tritium from the lithium-aluminum slugs irradiated in the second E-N core loading, and from the large batches of lithium-aluminum slugs irradiated as part of the blanket loading. Since these data complete the planned program of tritium analyses for the E-N demonstration load, it is felt appropriate that they be reported at this time. No further plutonium yield data have been received since issuance of the interim report and for this reason the plutonium conversion ratio is still tentative. It may be different when data from the second core test loading has been received.</p>A calorimetric measurement of the strong coupling constant in electron-positron annihilation at a center-of-mass energy of 91.6 GeV2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317887/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317887/"><img alt="A calorimetric measurement of the strong coupling constant in electron-positron annihilation at a center-of-mass energy of 91.6 GeV" title="A calorimetric measurement of the strong coupling constant in electron-positron annihilation at a center-of-mass energy of 91.6 GeV" src="https://digital.library.unt.edu/ark:/67531/metadc1317887/small/"/></a></p><p>In this work, a measurement of the strong coupling constant {alpha}{sub s} in e{sup +}e{sup {minus}} annihilation at a center-of-mass energy of 91.6 GeV is presented. The measurement was performed with the SLD at the Stanford Linear Collider facility located at the Stanford Linear Accelerator Center in California. The procedure used consisted of measuring the rate of hard gluon radiation from the primary quarks in a sample of 9,878 hadronic events. After defining the asymptotic manifestation of partons as `jets`, various phenomenological models were used to correct for the hadronization process. A value for the QCD scale parameter {Lambda}{sub bar MS}, defined in the {sub bar MS} renormalization convention with 5 active quark flavors, was then obtained by a direct fit to O({alpha}{sub s}{sup 2}) calculations. The value of {alpha}{sub s} obtained was {alpha}{sub s}(M{sub z0}) = 0.122 {plus_minus} 0.004 {sub {minus}0.007} {sup +0.008} where the uncertainties are experimental (combined statistical and systematic) and theoretical (systematic) respectively. Equivalently, {Lambda}{sub bar MS} = 0.28 {sub {minus}0.10}{sup +0.16} GeV where the experimental and theoretical uncertainties have been combined.</p>PT-IP-659-AC, Supplement A transition to normal discharge plan using striped target columns2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317888/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317888/"><img alt="PT-IP-659-AC, Supplement A transition to normal discharge plan using striped target columns" title="PT-IP-659-AC, Supplement A transition to normal discharge plan using striped target columns" src="https://digital.library.unt.edu/ark:/67531/metadc1317888/small/"/></a></p><p>The scheduled termination of PT IP-659-AC, presently being irradiated in F Reactor, will result in discharge of 105 columns of enriched uranium (0.947 w/o U-235) at less than 50 per cent of the goal exposure. The test block is currently scheduled to be replaced with natural uranium columns. Since F Reactor is on a semiblock discharge plan (alternate rows), subsequent operating plans would require that 64 of these replacement columns of natural uranium be likewise discharged during the scheduled outage in May of 1964 at less than 50 per cent of goal. It appears desirable to minimize the economic costs of the production test by an alternative discharge scheme (e.g., interim poison irradiation). The objective of this supplement is to soften the economic impact of low exposure fuel discharge scheduled by IP-659-AC and simultaneously to obtain a useful alternate product by irradiating nine columns of Li-Al and Bismuth in a ``striped`` charge.</p>Production of cobalt-602018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317889/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317889/"><img alt="Production of cobalt-60" title="Production of cobalt-60" src="https://digital.library.unt.edu/ark:/67531/metadc1317889/small/"/></a></p><p>Cobalt samples frequently are irradiated in nuclear reactors to produce gamma sources and can be irradiated as integral flux monitors because of the long half-life of the isotope produced. At the present time a small cobalt sample is being irradiated within the KW Reactor Snout facility for future use as a radiographic source for inspection of finished product in the Chemical Processing Department. Analysis was made to estimate the buildup of activity in this sample; the general equation may be of interest and value for other cobalt sample irradiations.</p>Physics aspects of operation in event of a large reactivity loss2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317894/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317894/"><img alt="Physics aspects of operation in event of a large reactivity loss" title="Physics aspects of operation in event of a large reactivity loss" src="https://digital.library.unt.edu/ark:/67531/metadc1317894/small/"/></a></p><p>The following information was prepared to assist the physicist who encounters a large reactivity lass as in a water soaked lattice or a more permanent loss as in the case of balls remaining in the pile after a ball drop. The discussion is based on experience gained during F Reactor`s severe water leak of July 27, 1961.</p>Atomic and electronic structure of metals and alloys: Rare earths, ultrathin films and surface alloys. Final report, [October 1, 1988--December 31, 1993]2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317895/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317895/"><img alt="Atomic and electronic structure of metals and alloys: Rare earths, ultrathin films and surface alloys. Final report, [October 1, 1988--December 31, 1993]" title="Atomic and electronic structure of metals and alloys: Rare earths, ultrathin films and surface alloys. Final report, [October 1, 1988--December 31, 1993]" src="https://digital.library.unt.edu/ark:/67531/metadc1317895/small/"/></a></p><p>The project has been productive: 47 refereed publications in about 5 years. While confined to the area of surfaces and thin films, the project has covered a wide range of physical properties and different materials: rare earths, bulk and surface alloys, metal surfaces, magnetism, and (especially) atomic and electronic structure of ultrathin films. Notable achievements include quantitative studies of atomic structure of clean rare-earth surfaces: Tb(0001), Tb(11{ovr 2}0), Gd(0001), and Gd(11{ovr 2}0). Surface alloys studied included Cu{l_brace}001{r_brace}c(2 {times} 2)-Au and Cu{l_brace}001{r_brace}c(2 {times} 2)-Pd. The most important achievement of the project lies in the application of quantitative low-energy electron diffraction to ultrathin films, particularly magnetic metals on nonmagnetic substrates (e.g., Fe on Ag{l_brace}001{r_brace}, etc.) (No data given.)</p>Full-scale demonstration Low-NO{sub x} Cell{trademark} Burner retrofit. Quarterly report No. 4, July 1, 1991--September 30, 19912018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317896/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317896/"><img alt="Full-scale demonstration Low-NO{sub x} Cell{trademark} Burner retrofit. Quarterly report No. 4, July 1, 1991--September 30, 1991" title="Full-scale demonstration Low-NO{sub x} Cell{trademark} Burner retrofit. Quarterly report No. 4, July 1, 1991--September 30, 1991" src="https://digital.library.unt.edu/ark:/67531/metadc1317896/small/"/></a></p><p>The overall objectives of the full-Scale Low-NOx Cell{trademark} Burner (LNCB{trademark}) Retrofit project is to demonstrate the cost-effective reduction of NOx generated by a large, base-loaded (70% capacity factor or greater), coal-fired utility boiler. Specific objectives include: (1) At least 50% NOx reduction over standard two-nozzle cell burners, without degradation of boiler performance or life; (2) acquire and evaluate emission and boiler performance data before and after the retrofit to determine NOx reduction and impact on overall boiler performance; (3) demonstrate that the LNCB{trademark} retrofits are the most cost-effective alternative to emerging, or commercially-available NOx control technology for units equipped with cell burners. The focus of this demonstration is to determine maximum NOx reduction capabilities without adversely impacting plant performance, operation and maintenance.</p>Burnup credit validation of SCALE-4 using light-water-reactor criticals2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317897/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317897/"><img alt="Burnup credit validation of SCALE-4 using light-water-reactor criticals" title="Burnup credit validation of SCALE-4 using light-water-reactor criticals" src="https://digital.library.unt.edu/ark:/67531/metadc1317897/small/"/></a></p><p>The ANSI/ANS 8.1 criticality safety standard recommends validation and benchmarking of the calculational methods used in evaluating criticality safety limits for away-from-reactor applications. The lack of critical experiments with burned light-water reactor (LWR) fuel in racks or in casks necessitates the validation of burnup credit methods by comparison with LWR core criticals. These benchmarks are relevant because they test a methodology`s ability to predict spent fuel isotopic and to evaluate the reactivity effects of heterogeneities and strong absorbers. Data are available to perform analyses at precise state points. As part of the Burnup Credit Analysis Verification (BCAV) Task, the U.S. Department of Energy has sponsored analysis of selected reactor core critical configurations from commercial pressurized-water-reactors (PWRs). The initial analysis methodology used the SCALE-4 code system to analyze a set of reactor critical configurations from Virginia Power`s Slurry and North Anna reactors. However, the analysis procedure was complex and included the calculation of lumped fission products. The methodology has since been revised to simplify both the data requirements and the calculational procedure for the criticality analyst. This revised methodology is validated here by a comparison with three reactor critical configurations from Tennessee Valley Authority`s Sequoyah Unit 2 Cycle 3 and two from Virginia Power`s Slurry Unit 1 Cycle 2.</p>RIVER-RAD: A computer code for simulating the transport of radionuclides in rivers2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317898/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317898/"><img alt="RIVER-RAD: A computer code for simulating the transport of radionuclides in rivers" title="RIVER-RAD: A computer code for simulating the transport of radionuclides in rivers" src="https://digital.library.unt.edu/ark:/67531/metadc1317898/small/"/></a></p><p>A screening-level model, RIVER-RAD, has been developed to assess the potential fate of radionuclides released to rivers. The model is simplified in nature and is intended to provide guidance in determining the potential importance of the surface water pathway, relevant transport mechanisms, and key radionuclides in estimating radiological dose to man. The purpose of this report is to provide a description of the model and a user`s manual for the FORTRAN computer code.</p>Experimental and theoretical investigation of operational and survivability issues in thermal radiators for thermionic space nuclear power systems. Final report2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317915/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317915/"><img alt="Experimental and theoretical investigation of operational and survivability issues in thermal radiators for thermionic space nuclear power systems. Final report" title="Experimental and theoretical investigation of operational and survivability issues in thermal radiators for thermionic space nuclear power systems. Final report" src="https://digital.library.unt.edu/ark:/67531/metadc1317915/small/"/></a></p><p>Heat pipes are a promising candidate for spacecraft radiators. This report describes a program designed to investigate the mass migration phenomenon in heat pipes. The program involved experiments to observe and measure the mass migration rates in both high and low operating temperature heat pipes. The low-temperature experiments were intended to simulate the operation of high-temperature, liquid metal heat pipes. Octadecane was the selected low-temperature working fluid. It is a paraffin and exhibits some of the characteristics of liquid metal working fluids. Sodium was the working fluid used in the high temperature experiment. A one-dimensional compressible flow model was developed for describing the hydrodynamics of rarefied vapor flow in heat pipe condensers. This model was compared with experimental data for the low-temperature octadecane heat pipes and the high-temperature sodium heat pipe. The model was found to satisfactorily predict the temperature profiles and location of freeze-fronts for the low-temperature heat pipes. Mass migration rate predictions using the model were satisfactory for the low-temperature heat pipes as well. However, the mass migration prediction for the high-temperature, sodium heat pipe was not in agreement with experimental data. An analytical model which accounts for property variations in the radial as well as longitudinal directions is recommended. A one-dimensional model was unsatisfactory for predicting mass migration rates in liquid metal heat pipes.</p>Supplement A to PT-IP-572-A effect of eccentricity on the irradiation behavior of KVNS fuel elements2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317916/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317916/"><img alt="Supplement A to PT-IP-572-A effect of eccentricity on the irradiation behavior of KVNS fuel elements" title="Supplement A to PT-IP-572-A effect of eccentricity on the irradiation behavior of KVNS fuel elements" src="https://digital.library.unt.edu/ark:/67531/metadc1317916/small/"/></a></p><p>With the use of smooth-bore Zircaloy-2 process tubes and self- supported fuel elements on a large scale at the K Reactors, establishment of the operating characteristics of this fuel element-process tube configuration is imperative. Under authority of Production Test-IP-409-A, two smooth-bore Zircaloy-2 tubes were routinely charged with KVNS fuel elements. Approximately 520 KVNS fuel elements have been irradiated in this facility. In Production Test-IP-572-A, the coolant temperature distribution in the annulus of the KVNS fuel element-process tube system is being evaluated as a function of fuel element support height. This production test supplement will provide data for further defining the operational characteristics of the self-support fuel element concept.</p>Deposition and properties of novel nitride superlattice coatings. Progress report, September 28, 1990--April 19932018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317917/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317917/"><img alt="Deposition and properties of novel nitride superlattice coatings. Progress report, September 28, 1990--April 1993" title="Deposition and properties of novel nitride superlattice coatings. Progress report, September 28, 1990--April 1993" src="https://digital.library.unt.edu/ark:/67531/metadc1317917/small/"/></a></p><p>We have carried out detailed studies of the processing, structure, and properties of certain polycrystalline superlattice coatings, including TiN/NbN, TiN/VN, TiN/Ni, and TiN/NiCr, which were produced using an opposed, dual-cathode, high-rate, reactive, unbalanced-magnetron sputtering system. The coatings exhibited hardness values as high as 5200 kgf/mm{sup 2} for TiN/NbN, 5100 for TiN/VN, 3500 for TiN/Ni, and 3200 for TiN/NiCr. These hardness values are all twice higher than their corresponding rule-of-mixture hardness values. The structure and properties of the coatings are a strong function of superlattice period, partial pressure of N{sub 2}, and energy and flux of ion bombardment during deposition. Possible mechanisms for hardness enhancement in the polycrystalline superlattice appear to be a result of dislocation blocking due to coherency strains, difference in dislocation line energies between layers, and small grain sizes. In response to high interest shown by industry, BIRL formed a 2-year Industrial Group Program, currently with 12 members, to transfer the superlattice coating technology.</p>Direct Methane Conversion to Methanol. Quarterly Project Status Report, October 1, 1992--December 31, 19922018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317918/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317918/"><img alt="Direct Methane Conversion to Methanol. Quarterly Project Status Report, October 1, 1992--December 31, 1992" title="Direct Methane Conversion to Methanol. Quarterly Project Status Report, October 1, 1992--December 31, 1992" src="https://digital.library.unt.edu/ark:/67531/metadc1317918/small/"/></a></p><p>We proposed to demonstrate the effectiveness of a catalytic membrane reactor (a ceramic membrane combined with a catalyst) to selectively produce methanol by partial oxidation of methane. Methanol is used as a chemical feedstock, gasoline additive, and turbine fuel. Methane partial oxidation using a catalytic membrane reactor has been determined as one of the promising approaches for methanol synthesis from methane. In the original proposal, the membrane was used to be used to selectively remove methanol from the reaction zone before carbon oxides form, thus increasing the methanol yield. Methanol synthesis and separation in one step would also make methane more valuable for producing chemicals and fuels. The cooling tube inserted inside the membrane reactor has created a low temperature zone that rapidly quenches the product stream. This system has proved effective for increasing methanol selectivity during CH{sub 4} oxidation, and we are using and modifying this non-isothermal, non-permselective membrane reactor.</p>Effect of 6.6 pH process water on process tube and fuel element corrosion2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317919/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317919/"><img alt="Effect of 6.6 pH process water on process tube and fuel element corrosion" title="Effect of 6.6 pH process water on process tube and fuel element corrosion" src="https://digital.library.unt.edu/ark:/67531/metadc1317919/small/"/></a></p><p>Reduction of the reactor process water pH from 6.9 to 6.6 at 100-B, D, DR, KF, and H currently is proposed in order to reduce the aluminum corrosion rate and the resultant outage time for water leaks, fuel ruptures, and process tube replacement. This document reviews the current knowledge of the effect of reducing the pH to 6.6 on aluminum corrosion. An estimate of the expected costs and benefits is included.</p>B Plant treatment, storage, and disposal (TSD) units inspection plan2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317920/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317920/"><img alt="B Plant treatment, storage, and disposal (TSD) units inspection plan" title="B Plant treatment, storage, and disposal (TSD) units inspection plan" src="https://digital.library.unt.edu/ark:/67531/metadc1317920/small/"/></a></p><p>This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ``Dangerous Waste Regulations`` (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements.</p>DC CICC retrofit magnet preliminary design, software development and analysis report. Quarterly progress report, January 19922018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317921/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317921/"><img alt="DC CICC retrofit magnet preliminary design, software development and analysis report. Quarterly progress report, January 1992" title="DC CICC retrofit magnet preliminary design, software development and analysis report. Quarterly progress report, January 1992" src="https://digital.library.unt.edu/ark:/67531/metadc1317921/small/"/></a></p><p>The proposed retrofit coil is made of superconducting Cable-in-Conduit Conductor (CICC). The coils are designed to produce a nominal vertical field of 4.5 tesla within the MHD channel based on a nominal current density of 13.05 MA/m{sup 2}. The coils are supported within a case, or so-called constant tension strap. When the magnet is energized, the electromagnetic J {times} B body forces push the winding pack laterally outward and vertically towards the machine`s midplane, thus putting the strap in tension. The end turns add axial tension to the conductor (a condition which is not simulated by this 2-D model of the midlength cross section). A sketch of the magnet system and structure is shown in Fig. 1.0-1. The purpose of this report is to describe the progress made in the design and analysis of the DC CICC retrofit magnet, and to outline the proposed next step.</p>Beat wave current drive experiment on the Davis Diverted Tokamak (DDT). Final report2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317922/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317922/"><img alt="Beat wave current drive experiment on the Davis Diverted Tokamak (DDT). Final report" title="Beat wave current drive experiment on the Davis Diverted Tokamak (DDT). Final report" src="https://digital.library.unt.edu/ark:/67531/metadc1317922/small/"/></a></p><p>The beatwave current drive experiment is summarized. The first phase of the experiment was the construction of the microwave sources and the diagnostics needed to demonstrate the beat wave effects, i.e. the measurement of the electrostatic plasma wave produced by the beating of two high intensity electromagnetic waves. In order to keep the cost of the experiments to a minimum, a low density filament plasma source (10{sup 8}) to (10{sup 10} particles cm{sup {minus}3}) was employed and the magnetic field in the toroidal plasma was produced by a dc power supply.</p>SSC 50 mm collider dipole cryostat design2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317923/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317923/"><img alt="SSC 50 mm collider dipole cryostat design" title="SSC 50 mm collider dipole cryostat design" src="https://digital.library.unt.edu/ark:/67531/metadc1317923/small/"/></a></p><p>The cryostat of a Superconducting Super Collider (SSC) dipole magnet consists of all magnet components except the magnet assembly itself. It serves to support the magnet accurately and reliably within the vacuum vessel, provide all required cryogenic piping, and to insulate the cold mass from heat radiated and conducted from the environment. It must function reliably during storage, shipping and handling, normal magnet operation, quenches, and seismic excitations, and must be manufacturable at low cost. The major components of the cryostat are the vacuum vessel, thermal shields, multilayer insulation system, cryogenic piping, interconnections, and suspension system. The overall design of a cryostat for superconducting accelerator magnets requires consideration of fluid flow, proper selection of materials for their thermal and structural performance at both ambient and operating temperature, and knowledge of the environment to which the magnets will be subjected over the course of their expected operating life. This paper describes the design of the current SSC dipole magnet cryostat and includes discussions on the structural and thermal considerations involved in the development of each of the major systems.</p>Coal combustion: Effect of process conditions on char reactivity. Sixth quarterly technical report, December 1, 1992--March 1, 19932018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317924/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317924/"><img alt="Coal combustion: Effect of process conditions on char reactivity. Sixth quarterly technical report, December 1, 1992--March 1, 1993" title="Coal combustion: Effect of process conditions on char reactivity. Sixth quarterly technical report, December 1, 1992--March 1, 1993" src="https://digital.library.unt.edu/ark:/67531/metadc1317924/small/"/></a></p><p>During the past quarter, we developed the image analysis procedure for obtaining the transient swelling patterns of pyrolyzing coal particles. Pyrolysis experiments were videotaped and a sequence of digital images was acquired from each experiment tape at rates of 1.5 to 6 images per second. These digital images were then processed to measure the size and shape of pyrolyzing particles as a function of pyrolysis temperature. A systematic analysis of the transient swelling patterns showed significant differences among runs carried out at different heating rates. At low heating rates (1{degree}C/s), the particles swelled rapidly to their maximum size. This initial swelling was followed by a ``bubbling`` phase during which the particles underwent a rapid sequence of expansions and contractions as bubbles of volatiles grew in the particle interior and broke through their surface. The particle size then decreased to show a small final swelling. At higher heating rates, the particle size decreased significantly during the ``bubbling`` phase and the final swelling was higher. A systematic comparison of particle swelling and devolatilization rates is also presented.</p>{sup 235}U accountability measurements on small samples2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317925/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317925/"><img alt="{sup 235}U accountability measurements on small samples" title="{sup 235}U accountability measurements on small samples" src="https://digital.library.unt.edu/ark:/67531/metadc1317925/small/"/></a></p><p>Savannah River Site (SRS) is improving uranium accountability at its fuel fabrication facility through measurements of {sup 235}U in samples taken from uranium/aluminum alloy melts. Since area personnel desired a method that would minimize mixed waste, low volume samples are prepared from dissolutions of production melt grab samples. The solution assay monitor (SAM) analyzes for {sup 235}U gamm-rays by using a high-efficiency germanium well detector. The detector`s high counting efficiency permits analysis of small samples (7 mL) from these dissolutions, and the counting geometry minimizes sample geometry uncertainties. Counting each sample for thirty minutes delivers excellent precision across the calibration range of 3 to 12 g uranium per liter. As shown by interlaboratory calibration, the gamma-ray spectrometer provides overall (counting, calibration, geometric,...) uncertainties less than 0.7% one sigma. Gamma-rays from a reference source, used to provide live-time corrections, are collimated to avoid absorption by the sample in the detector well. Since sample masses are small, minor self-attenuation corrections are calculated from chemical composition data rather than determined in separate transmission measurements. This avoids employing short-lived transmission sources for self-attenuation corrections.</p>Linking science more closely to policy-making: Global climate change and the national reorganization of science and technology policy2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317926/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317926/"><img alt="Linking science more closely to policy-making: Global climate change and the national reorganization of science and technology policy" title="Linking science more closely to policy-making: Global climate change and the national reorganization of science and technology policy" src="https://digital.library.unt.edu/ark:/67531/metadc1317926/small/"/></a></p><p>This paper examines the national trends behind recent efforts to link science and technology more closely to policy-making. It describes the politics surrounding the establishment of the National Science and Technology Council and its committee on Environment and Natural Resources (of which the global change program is a part). It discusses the evolution of the ``assessments`` function within the climate change program in general, and within the Department of Energy, in particular, and how the Clinton Administration`s approach to climate change ``assessments`` function within the climate change program in general, and within the Department of Energy, in particular, and how the Clinton Administration`s approach to climate change ``assessments`` differs from that of its predecessor. The paper concludes with a critique both of the national reorganization of science and technology policy and of the assessments component of the climate change program.</p>Re-evaluation of metal performance levels of C-II-N and C-II-E material2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317930/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317930/"><img alt="Re-evaluation of metal performance levels of C-II-N and C-II-E material" title="Re-evaluation of metal performance levels of C-II-N and C-II-E material" src="https://digital.library.unt.edu/ark:/67531/metadc1317930/small/"/></a></p><p>This report presents an analysis of rupture experience at C Reactor over the past two years. The purpose of the study was to provide a basis for revising, if necessary, the current metal performance level multipliers for C-II-N and C-II-E material.</p>Project W-314 specific test and evaluation plan for 241-AY-01A pump pit upgrade2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317931/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317931/"><img alt="Project W-314 specific test and evaluation plan for 241-AY-01A pump pit upgrade" title="Project W-314 specific test and evaluation plan for 241-AY-01A pump pit upgrade" src="https://digital.library.unt.edu/ark:/67531/metadc1317931/small/"/></a></p><p>This Specific Test and Evaluation Plan (STEP) defines the test and evaluation activities encompassing the upgrade of the 241-AY-0IA Pump Pit for the W-314 Project. The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AY-01A Pump Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system`s performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP).</p>Laboratory studies of spectroscopic markers for the characterization of surface erosion by plasmas2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317932/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317932/"><img alt="Laboratory studies of spectroscopic markers for the characterization of surface erosion by plasmas" title="Laboratory studies of spectroscopic markers for the characterization of surface erosion by plasmas" src="https://digital.library.unt.edu/ark:/67531/metadc1317932/small/"/></a></p><p>The erosion rates in portions of fusion plasma devices like the ITER tokamak are sufficiently high that nearly real-time information on cumulative removal is needed for control and machine safety. We are developing a digitally--encoded scheme to indicate the depth of erosion at numerous poloidal and toroidal locations around ITER. The scheme uses materials embedded in the walls and divertors, which, when uncovered, present remotely detectable signals. This paper reports laboratory experiments on prototype markers consisting of combinations of up to 5 elements (Au,Pd,Ag,In,Ga) along with Au,Pt, and Ta pure metals. The markers were bonded to 4-D carbon-carbon composite of the type proposed for use in the ITER first wall, and placed in the lower-hybrid-driven plasma of the atomic beam facility at PPL. The paper describes this device Light emission was characterized using a 1 meter Czerny-Turner vacuum ultraviolet monochromator. The samples were characterized both before and after plasma exposure by Auger spectroscopy. We report the time-dependent behavior of the spectra of the visible and ultraviolet light emitted by the plasma when the markers are uncovered by the erosion showing emission lines of the marker elements which are easily distinguished from the background plasma lines. The dependence of the light intensity on bias voltage is compared to the known sputtering yields of the elements. The optical detection method allows exploration of the threshold dependence of these multi-element targets. An exponential dependence of yield above threshold was observed for all of the elements studied.</p>Participation in Multilateral Effort to Develop High Performance Integrated CPC Evacuated Collectors. Final Report, July 1, 1986--May 31, 19872018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317933/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317933/"><img alt="Participation in Multilateral Effort to Develop High Performance Integrated CPC Evacuated Collectors. Final Report, July 1, 1986--May 31, 1987" title="Participation in Multilateral Effort to Develop High Performance Integrated CPC Evacuated Collectors. Final Report, July 1, 1986--May 31, 1987" src="https://digital.library.unt.edu/ark:/67531/metadc1317933/small/"/></a></p><p>The University of Chicago Solar Energy Group has had a continuing program and commitment to develop an advanced evacuated solar collector integrating nonimaging concentration into its design. During the period from 1985--1987, some of our efforts were directed toward designing and prototyping a manufacturable version of an Integrated Compound Parabolic Concentrator (ICPC) evacuated collector tube as part of an international cooperative effort involving six organizations in four different countries. This ``multilateral`` project made considerable progress towards a commercially practical collector. One of two basic designs considered employed a heat pipe and an internal metal reflector CPC. We fabricated and tested two large diameter (125mm) borosilicate glass collector tubes to explore this concept. The other design also used a large diameter (125mm) glass tube but with a specially configured internal shaped mirror CPC coupled to a U-tube absorber. Performance projections in a variety of systems applications using the computer design tools developed by the International Energy Agency (IEA) task on evacuated collectors were used to optimize the optical and thermal design. The long-term goal of this work continues to be the development of a high efficiency, low cost solar collector to supply solar thermal energy at temperatures up to 250{degree}C. Some experience and perspectives based on our work are presented and reviewed. Despite substantial progress, the stability of research support and the market for commercial solar thermal collectors were such that the project could not be continued. A cooperative path involving university, government and industrial collaboration remains the most attractive near term option for developing a commercial ICPC.</p>Radiation hardening and radiation-induced chromium depletion effects on intergranular stress corrosion cracking of austenitic stainless steels2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317934/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317934/"><img alt="Radiation hardening and radiation-induced chromium depletion effects on intergranular stress corrosion cracking of austenitic stainless steels" title="Radiation hardening and radiation-induced chromium depletion effects on intergranular stress corrosion cracking of austenitic stainless steels" src="https://digital.library.unt.edu/ark:/67531/metadc1317934/small/"/></a></p><p>Available data on neutron-irradiated materials have been analyzed and correlations developed between fluence, yield strength, grain boundary chromium concentration and cracking susceptibility in high-temperature water environments. Large heat-to-heat differences in critical fluence (0.2 to 2.5 n/cm{sup 2}) for IGSCC are documented.In many cases, this variability is consistent with yield strength differences among irradiated materials. IGSCC correlated better to yield strength than to fluence for most heats suggesting a possible role of the radiation-induced hardening (and microstructure) on cracking. However, isolatedheats reveal a wide range of yield strengths from 450 to 800 MPa necessary to promote IGSCC which cannot be understood by strength effects alone. Grain boundary Cr depletion explain differences in IGSCC susceptibility for irradiated stainless steels. Cr contents versus SCC shows that all materials showing IG cracking have some grain boundary depletion ({ge}2%). Grain boundary Cr concentrations for cracking (below {approximately}16 wt %) are in good agreement with similar SCC tests on unirradiated 304 SS with controlled depletion profiles. Heats that prompt variability in the yield strength correlation, are accounted for bydifferences in their interfacial Cr contents. Certain stainless steels are more resistant to cracking even though they have significant radiation-induced Cr depletion. It is proposed that Cr depletion is required for IASCC, but observed susceptibility is modified by other microchemical and microstructural components.</p>Bed material agglomeration during fluidized bed combustion. Technical progress report, October 1, 1993--December 31, 19932018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317937/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317937/"><img alt="Bed material agglomeration during fluidized bed combustion. Technical progress report, October 1, 1993--December 31, 1993" title="Bed material agglomeration during fluidized bed combustion. Technical progress report, October 1, 1993--December 31, 1993" src="https://digital.library.unt.edu/ark:/67531/metadc1317937/small/"/></a></p><p>During this quarter, agglomerates which formed in the FBC at Montana-Dakota Utilities (Heskett Station Unit 2 located in Bismarck, ND) were analyzed by x-ray diffraction analyses (XRD) for mineral determination; bulk chemical composition was determined by inductively coupled plasma spectroscopy; and polished sections were made for optical and scanning electron microscopy. Polarized-light microscopy was performed using a Zeiss research microscope. Individual mineral grains were analyzed using an ARL electron microprobe and a JOEL 840 scanning electron microscope. The agglomerate was found in the mechanical dust collector and was about ten centimeters in diameter with a dark-colored core and a greenish rim. The sample had voids up to ten millimeters in size; however, the agglomerate was hard to break apart. Bulk compositionally, the agglomerate consists primarily of calcium, silica, and alumina with relatively high abundances of iron (8 to 9 wt %), magnesium (5 to 9 wt %) and sodium (3 to 4 wt %). It is likely that the ``root`` cause of this agglomerate originated in the dense phase of the FBC bed. Because fluidized bed combustors work below the ash fusion temperature of coal ash, aluminosilicates (clays) in the ash probably became ``sticky`` due to fluxing reactions with pyrite (FeS{sub 2}) and perhaps alkalies (Na). This is indicated by the high amounts of iron, silica, and alumina in the agglomerate. Because of the size of the deposit, the bed particles probably agglomerated in the dust collector.</p>Achieving high fusion reactivity in high poloidal beta discharges in TFTR2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317890/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317890/"><img alt="Achieving high fusion reactivity in high poloidal beta discharges in TFTR" title="Achieving high fusion reactivity in high poloidal beta discharges in TFTR" src="https://digital.library.unt.edu/ark:/67531/metadc1317890/small/"/></a></p><p>High poloidal beta discharges have been produced in TFTR that achieved high fusion reactivities at low plasma currents. By rapidly decreasing the plasma current just prior to high-power neutral beam injection, relatively peaked current profiles were created having high l{sub i} > 2, high Troyon-normalized beta, {beta}N > 3, and high poloidal beta. {beta}{sub p} {ge} 0.7 R/a. The global energy confinement time after the current ramp was comparable to supershots, and the combination of improved MHD stability and good confinement produced a new high {epsilon}{beta}{sub p} high Q{sub DD} operating mode for TFTR. Without steady-state current profile control, as the pulse lengths of high {beta}p discharges were extended, l{sub i} decreased, and the improved stability produced immediately after by the current ramp deteriorated. In four second, high {epsilon}{beta}{sub p} discharges, the current profile broadened under the influence of bootstrap and beam-drive currents. When the calculated voltage throughout the plasma nearly vanished, MHD instabilities were observed with {beta}{sub N} as low as 1.4. Ideal MHD stability calculations showed this lower beta limit to be consistent with theoretical expectations.</p>Laboratory-scale vitrification and leaching of Hanford high-level waste for the purpose of simulant and glass property models validation2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317891/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317891/"><img alt="Laboratory-scale vitrification and leaching of Hanford high-level waste for the purpose of simulant and glass property models validation" title="Laboratory-scale vitrification and leaching of Hanford high-level waste for the purpose of simulant and glass property models validation" src="https://digital.library.unt.edu/ark:/67531/metadc1317891/small/"/></a></p><p>The Hanford Waste Vitrification Plant (HWVP) is being built to process the high-level and TRU waste into canistered glass logs for disposal in a national repository. Testing programs have been established within the Project to verify process technology using simulated waste. A parallel testing program with actual radioactive waste is being performed to confirm the validity of using simulates and glass property models for waste form qualification and process testing. The first feed type to be processed by and the first to be tested on a laboratory-scale is pretreated neutralized current acid waste (NCAW). The NCAW is a neutralized high-level waste stream generated from the reprocessing of irradiated nuclear fuel in the Plutonium and Uranium Extraction (PUREX) Plant at Hanford. As part of the fuel reprocessing, the high-level waste generated in PUREX was denitrated with sugar to form current acid waste (CAW). Sodium hydroxide and sodium nitrite were added to the CAW to minimize corrosion in the tanks, thus yielding neutralized CAW. The NCAW contains small amounts of plutonium, fission products from the irradiated fuel, stainless steel corrosion products, and iron and sulfate from the ferrous sulfamate reductant used in the PUREX process. This paper will discuss the results and status of the laboratory-scale radioactive testing.</p>Analysis of natural convection in a waste glass melter2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317892/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317892/"><img alt="Analysis of natural convection in a waste glass melter" title="Analysis of natural convection in a waste glass melter" src="https://digital.library.unt.edu/ark:/67531/metadc1317892/small/"/></a></p><p>Laminar natural convection is a two-dimensional cavity with a line heat sink at the top boundary is investigated numerically. The fluid in the cavity is a high Prandtl number fluid with volumetric heat source. Parametric study is conducted to find the effect of variations in Rayleigh number, aspect ratio, sink location, and volumetric heat source on the flow and temperature field. 5 refs.</p>Production test IP-401-A: Irradiation of Zircaloy-2 jacketed UO{sub 2} tubular elements in the KER loops2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317893/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317893/"><img alt="Production test IP-401-A: Irradiation of Zircaloy-2 jacketed UO{sub 2} tubular elements in the KER loops" title="Production test IP-401-A: Irradiation of Zircaloy-2 jacketed UO{sub 2} tubular elements in the KER loops" src="https://digital.library.unt.edu/ark:/67531/metadc1317893/small/"/></a></p><p>The objective of this production test is to evaluate the behavior of large diameter tubular UO{sub 2} fuel elements during high temperature irradiation. Eighteen inch long tubular UO{sub 2} fuel elements 1.804 inch OD, 0.544 inch ID, in 0.060 inch Zircaloy-2 jackets will be irradiated in the KER loops either alone or in conjunction with other tests to exposures up to 3500 MWD/T of contained uranium.</p>Compton harmonic resonances, stochastic instabilities, quasilinear diffusion, and collisionless damping with ultra-high intensity laser waves2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317903/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317903/"><img alt="Compton harmonic resonances, stochastic instabilities, quasilinear diffusion, and collisionless damping with ultra-high intensity laser waves" title="Compton harmonic resonances, stochastic instabilities, quasilinear diffusion, and collisionless damping with ultra-high intensity laser waves" src="https://digital.library.unt.edu/ark:/67531/metadc1317903/small/"/></a></p><p>The dynamics of electrons in two-dimensional, linearly or circularly polarized, ultra-high intensity (above 10{sup 18}W/cm{sup 2}) laser waves, is investigated. The Compton harmonic resonances are identified as the source of various stochastic instabilities. Both Arnold diffusion and resonance overlap are considered. The quasilinear kinetic equation, describing the evolution of the electron distribution function, is derived, and the associated collisionless damping coefficient is calculated. The implications of these new processes are considered and discussed.</p>Early lung cancer detection in uranium miners with abnormal sputum cytology. Technical progress report, July 31, 1991--July 31, 19922018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317904/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317904/"><img alt="Early lung cancer detection in uranium miners with abnormal sputum cytology. Technical progress report, July 31, 1991--July 31, 1992" title="Early lung cancer detection in uranium miners with abnormal sputum cytology. Technical progress report, July 31, 1991--July 31, 1992" src="https://digital.library.unt.edu/ark:/67531/metadc1317904/small/"/></a></p><p>This work supported by the United States of Energy, continues to add data on the health affects of cigarette smoking and radon exposure on uranium miners. Since the last Technical Progress Report in July or 1991, 537 sputum cytology samples have been collected on the 300 uranium workers in the surveillance study. To date there are 436 lung cancer cases in the Uranium Miner Tumor Registry with diagnostic slides from surgery and/or autopsy; an additional 40 cases have been diagnosed with sputum cytology only. In March of 1991 the Geno Saccomanno Uranium Workers Archive was established at St. Mary`s Hospital and Medical Center as a depository for biological specimens and epidemiological data from the 17,700 uranium miners who have been a part or the study.</p>Extraction of tritium from (LiAlO{sub 2}) targets2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317905/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317905/"><img alt="Extraction of tritium from (LiAlO{sub 2}) targets" title="Extraction of tritium from (LiAlO{sub 2}) targets" src="https://digital.library.unt.edu/ark:/67531/metadc1317905/small/"/></a></p><p>This paper describes procedures which relate to the process of extracting tritium from irradiated lithium aluminate target elements.</p>Enhanced portability of safeguards measurements tools2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1317906/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1317906/"><img alt="Enhanced portability of safeguards measurements tools" title="Enhanced portability of safeguards measurements tools" src="https://digital.library.unt.edu/ark:/67531/metadc1317906/small/"/></a></p><p>In recent years, computers have decreased in size from cubic meter volumes to units that can fit in the palm of the hand. At the same time, the capability of the computers has increased due to both faster electronics and improvements in software. Similar changes have occurred in other electronic devices, primarily because of the decrease in size of the electronics and the incorporation of smart electronics (microprocessors). Similar decreases in the size of the detectors used in radiation detection, however, have not yet occurred. Reduction in detector size requires advances in materials to provide higher efficiency in a smaller volume. Improved intrinsic efficiency of detectors does not always meet safeguards needs because resolution of individual photopeaks may be more important than efficiency. Recent advances at the Pacific Northwest Laboratory have led to smaller multichannel analyzers and more compact detector electronics. In related studies, the performance of the new scintillation detectors has been explored.</p>