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Air Pollution and the Siting of Fossil Fuel Power Plants
The decision to locate a fossil-fueled electrical power plant on a particular site involves trade-offs among the costs of: (1) land acquisition, (2) plant construction, operation, and maintenance, (3) power transmission, and (4) air pollution damage to humans, animals, plants and materials. The fourth of these, pollution costs, has been of great concern in recent years. But seldom, if ever, are the specific dollar trade-offs between the environmental and the other costs associated with site selection taken into account. The sum of the costs of power generation (land, construction, operation, maintenance), power transmission, and air pollution damages (from sulfur dioxide, nitrogen oxides, and particulates) is the total social cost of a fossil-fuel plant; this total cost will generally vary by site. This paper presents an analysis of the total social cost, and the trade-offs between generation/transmission and air pollution costs, for various types of fossil plants at different sites in northern Illinois. The analysis identifies the combinations of site, fossil fuel, and sulfur dioxide (SO2) control technology that minimize total social costs.
An Algebraic Theory of Program Specification and Correctness Using Symmetry Operations
This report applies some methods from the theory of group representation to the questions of program specification and knowledge about programs. The theory is that of a program as a transformation on a state space, and operators commuting with that transformation being symmetries of the program, means of specifying properties, and generators of program invariants. Because a program can simulate a system in the real world, there is a corresponding model of engineered artifacts, that is, manmade objects having a theory for their design.
Algorithms for Automated Diagnosis of Faults in Physical Plant
This report presents a diagnostic automation that can be used to investigate classes of systems without feedback loops. This report shows the input needed for the automation, the algorithm used, and the PROLOG program for the simulation.
ALICE, A Hybrid Lagrangian-Eulerian Code for Calculating Fluid-Structure Interaction Transients in Fast-Reactor Containment
This report describes ALICE, which uses an arbitrary Lagrangian-Eulerian method to analyze the response of the contaminant vessel and other solid media inside a reactor contaminant.
Alternative Fuel Cycle Options : Performance Characteristics and Impact on Nuclear Power Growth Potential
The fuel utilization characteristics for LWR, SSCR, CANDU and LMFBR reactor concepts are quantified for various fuel cycle options, including once-through cycles, thorium cycles, and denatured cycles. The implications of various alternative reactor deployment strategies on the long-term nuclear power growth potential are then quantified in terms of the maximum nuclear capacity that can be achieved and the growth pattern over time, subject to the constraint of a fixed uranium-resource base. The overall objective of this study is to shed light on any large differences in the long-term potential that exist between various alternative reactor/fuel cycle deployment strategies.
An Alternative Library Under 4. 2 BSD UNIX on a VAX 11/780
This paper describes an alternative library of elementary functions prepared for use with the standard Fortran compiler under 4.2 BSD UNIX on a VAX 11/780. The library, written in C and based on the book ''Software Manual for the Elementary Functions'' by Cody and Waite, offers improved accuracy over the standard system library, as well as additional capabilities. Listings and output from the ELEFUNT suite of test programs are included in the appendix.
Alternatives for Conversion to Solid Interim Waste Forms of the Radioactive Liquid High-Level Wastes Stored at the Western New York Nuclear Service Center
Techniques for isolating and solidifying the nuclear wastes in the storage tanks at the Western New York Nuclear Service Center plant have been examined. One technique involves evaporating the water and forming a molten salt containing the precipitated sludge. The salt is allowed to solidify and is stored in canisters until processing into a final waste form is to be done. Other techniques involve calcining the waste material, then agglomerating the calcine with sodium silicate to reduce its dispersibility. This option can also involve a prior separation and decontamination of the supernatant salt. The sludge and all resins containing fission-product activity are then calcined together. The technique of removing the water and solidifying the salt may be the simplest method for removing the waste from the West Valley Plant.
Alternatives for Disposal of Raffinate from the TRUEX Process
Possible methods for disposing of the immobilized raffinate from TRUEX processing are reviewed. The purpose of the TRUEX process is to extract transuranium elements from high-level and TRU wastes into a small volume that can be managed at lower cost than that of the original wastes. The raffinate from the TRUEX process, containing negligible concentrations of transuranium elements, would be combined with salt solutions also derived from processing high-level waste, and the mixture would be converted to grout.
Analysis of a Cylindrical Shell Vibrating in a Cylindrical Fluid Region
Analytical and experimental methods are presented for evaluating the vibration characteristics of cylindrical shells such as the thermal liner of the Fast Flux Test Facility (FFTF) reactor vessel. The NASTRAN computer program is used to calculate the natural frequencies, mode shapes, and response to a harmonic loading of a thin, circular cylindrical shell situated inside a fluid-filled rigid circular cylinder. Solutions in a vacuum are verified with an exact solution method and the SAP IV computer code. Comparisons between analysis and experiment are made, and the accuracy and utility of the fluid-solid interaction package of NASTRAN is assessed.
Analysis of an Internally Pressurized Prismatic Cell Can
This report contains an elastic stress and displacement analysis of a prismatic cell can subjected to internal pressure. A computer program was written to perform the analysis. The results show that, for the geometry chosen, the thicknesses of the cell-can walls and the magnitude of the internal pressure are the most important parameters that determine the stresses and deformations of the cell can. Recommendations for future studies are included.
Analysis of Cracked Core Spray Injection Line Piping from the Quad Cities Units 1 and 2 Boiling Water Reactors
Elbow assemblies and adjacent piping from the loops A and B core spray injection lines of Quad Cities Units 1 and 2 Boiling Water Reactors have been examined in order to determine the nature and causes of coolant leakages and flaw indications detected during hydrostatic tests and subsequent ultrasonic inspections. The elbow assemblies were found to contain multiple intergranular cracks in the weld heat-affected zones. The cracking was predominantly axial in orientation in the forged elbow and wedge components, whereas mixed axial and circumferential cracking was seen in the wrought piping pieces. In at least two instances, axial cracks completely penetrated the circumferential weld joining adjacent components. Based upon the observations made in the present study, the failures were attributed to intergranular stress corrosion cracking caused by the weld-induced sensitized microstructure and residual stresses present; dissolved oxygen in the reactor coolant apparently served as the corrosive species. The predominantly axial orientation of the cracks present in the forged components is believed to be related to the banded microstructure present in these components. The metallographic studies reported are supplemented by x-radiography, chemical analysis and mechanical test results, determinations of the degree of sensitization present, and measurements of weld metal delta ferrite content.
Analysis of EBR-II Low-Power Dosimetry Run 78C
This report compares calculated reaction rates based on neutron-transport calculations in RZ and XY geometries with measured values from a low-power dosimetry test in EBR-II. Axial distributions of Uranium-235 and uranium-238 fission rates and uranium-238 capture rate are given for various radial locations along the length of the core and the axial reflectors, and along the length of the radial steel reflectors. Reaction rates, primarily at the reactor midplane, are given for a number of fission and capture reactions. The analytical RZ- and XY-geometry models used for the neutronics calculations are described.
An Analysis of Factors Influencing the Reliability of Retrievable Storage Canisters for Containment of Solid High-Level Radioactive Waste
The reliability of stainless steel type 304L canisters for the containment of solidified high-level radioactive wastes in the glass and calcine forms was studied. A reference system, drawn largely from information furnished by Battelle Northwest Laboratories and Atlantic Richfield Hanford Company is described. Operations include filling the canister with the appropriate waste form, interim storage at a reprocessing plant, shipment in water to a Retrievable Surface Storage Facility (RSSF), interim storage at the RSSF, and shipment to a final disposal facility.
Analysis of Heat-Pipe Absorbers in Evacuated-Tube Solar Collectors
Heat transfer in evacuated-tube solar collectors with heat-pipe absorbers is compared with that for similar collectors with flow-through absorbers. In systems that produce hot water or other heated fluids, the heat-pipe absorber suffers a heat transfer penalty compared with the flow-through absorber, but in many cases the penalty can be minimized by proper design at the heat-pipe condenser and system manifold. The heat transfer penalty decreases with decreasing collector heat loss coefficient, suggesting that evacuated tubes with optical concentration are more appropriate for use with heat pipes than evacuated or non-evacuated flat-plate collectors. When the solar collector is used to drive an absorption chiller, the heat-pipe absorber has better heat transfer characteristics than the flow-through absorbers.
Analysis of Nonlinear Fluid Structure Interaction Transient in Fast Reactors
A generalized Eulerian method is described for analyzing the fluid transients and the structural response in nuclear reactors under the postulated accident conditions. The phenomena considered are the wave propagation, slug impact, sodium spillage, bubble migration, and the fluid-structure interaction. The basic equations and numerical formulation are presented in detail. Sample calculations are given to illustrate the analysis. It is shown from the results that the implicit, iterative method used is unconditionally stable and is especially suitable for problems involving large material distortions.
Analysis of Proposed Gamma-Ray Detection System for the Monitoring of Core Water Inventory in a Pressurized Water Reactor
An initial study has been performed of the feasibility of employing an axial array of gamma detectors located outside the pressure vessel to monitor the coolant in a PWR. A one-dimensional transport analysis model is developed for the LOFT research reactor and for a mock-PWR geometry. The gamma detector response to coolant voiding in the core and down-comer has been determined for both geometries. The effects of various conditions (for example, time after shutdown, materials in the transport path, and the relative void fraction in different water regions) on the detector response are studied. The calculational results have been validated by a favorable comparison with LOFT experimental data. Within the limitations and approximations considered in the analysis, the results indicate that the gamma-ray detection scheme is able to unambiguously respond to changes in the coolant inventory within any vessel water region.
An Analysis of the High-Temperature Particulate Collection Problem
Particulate agglomeration and separation at high temperatures and pressures are examined, with particular emphasis on the unique features of the direct-cycle application of fluidized-bed combustion. The basic long-range mechanisms of aerosol separation are examined, and the effects of high temperature and high pressure on usable collection techniques are assessed. Primary emphasis is placed on those avenues that are not currently attracting widespread research. The high-temperature, particulate-collection problem is surveyed, together with the peculiar requirements associated with operation of turbines with particulate-bearing gas streams.
Analysis of the October 5, 1979 Lithium Spill and Fire in the Lithium Processing Test Loop
On October 5, 1979, the Lithium Processing Test Loop (LPTL) developed a lithium leak in the electromagnetic (EM) pump channel, which damaged the pump, its surrounding support structure, and the underlying floor pan. A thorough analysis of the causes and consequences of the pump failure was conducted by personnel from CEN and several other ANL divisions. Metallurgical analyses of the elliptical pump channel and adjacent piping revealed that there was a significant buildup of iron-rich crystallites and other solid material in the region of the current-carrying bus bars (region of high magnetic field), which may have resulted in a flow restriction that contributed to the deterioration of the channel walls. The location of the failure was in a region of high residual stress (due to cold work produced during channel fabrication); this failure is typical of other cold work/stress-related failures encountered in components operated in forced-circulation lithium loops. Another important result was the isolation of crystals of a compound characterized as Li/sub x/CrN/sub y/. Compounds of this type are believed to be responsible for much of the Fe, Cr, and Ni mass transfer encountered in lithium loops constructed of stainless steel. The importance of nitrogen in the mass-transfer mechanism has long been suspected, but the existence of stable ternary Li-M-N compounds (M = Fe, Cr, Ni) had not previously been verified.
Analytical and Experimental Investigation of a Nuclear Reactor Support Structure
Report containing experiments regarding the slopes and deflections of different grid support structures for a nuclear reactor.
Analytical Electron Microscopy Characterization of Fernald soils. Annual Report, October 1993 - September 1994
A combination of backscattered electron imaging and analytical electron microscopy (AEM) with electron diffraction have been used to determine the physical and chemical properties of uranium contamination in soils from the Fernald Environmental Management Project in Ohio. The information gained from these studies has been used in the development and testing of remediation technologies.
Analytical Electron Microscopy Characterization of Uranium-Contaminated Soils from the Fernald Site, FY1993 Report
A combination of optical microscopy, scanning electron microscopy with backscattered electron detection (SEM/BSE), and analytical electron microscopy (AEM) is being used to determine the nature of uranium in soils from the Fernald Environmental Management Project. The information gained from these studies is being used to develop and test remediation technologies. Investigations using SEM have shown that uranium is contained within particles that are typically 1 to 100 micrometers in diameter. Further analysis with AEM has shown that these uranium-rich regions are made up of discrete uranium-bearing phases. The distribution of these uranium phases was found to be inhomogeneous at the microscopic level.
Analytical Investigation of Certain Aspects of LMFBR Subassembly-Failure Propagation
An analytical investigation of certain problems in the area of subassembly-to-subassembly failure propagation in LMFBR's is described. Existing analyses of the response of the adjacent subassembly duct to mechanical loads are reviewed and summarized, and major uncertainties are identified. Additional analyses of the response of the adjacent subassembly to certain thermal loads are presented in two parts. In the first part, the effect of an external heat flux on duct melting and thermal stresses is considered. The external heat fluxes required to produce duct melting or excessive thermal stresses are compared with the heat fluxes that might be expected from the molten fuel deposited on the duct wall. In the second part, a thermal-hydraulic study is performed to investigate the effect of the external heat flux on the coolant temperature distribution in the adjacent subassembly. Both normal subassembly geometry and distorted subassembly geometry are considered. A detailed model of the coolant region formed by the heated duct wall and the displaced fuel pins is also analyzed to determine whether there are severe temperature gradients.
An Analytical Study of the Feasibility of Irradiating U233/Th232 Metal Fuel Experiments in EBR-II
Recent concerns about the proliferation and diversion of plutonium have lead to reconsideration of Uranium-233/Thorium-232 fuel cycles. Although thorium fuels have been studied earlier, much of that work is incomplete; consequently, additional irradiation studies will be necessary.
Analytical Techniques for Ambient Sulfate Aerosols
This report describes the work done to further develop the infrared spectroscopic analytical method for the analysis of atmospheric aerosol particles, as well as some exploratory work on a new procedure for determining proton acidity in aerosol samples. Earlier work had led to the successful use of infrared (ir) spectrophotometry for the analysis of nitrate, ammonium, and neutral and acidic sulfates in aerosol samples collected by an impactor on a Mylar-film substrate. In this work, a filter-extraction method was developed to prepare filter-collected aerosol samples for ir analysis. A study was made comparing the ir analytical results on filter-collected samples with impactor-collected samples. Also, the infrared analytical technique was compared in field studies with light-scattering techniques for aerosol analysis. A highly sensitive instrument for aerosol analysis using attenuated total internal reflection (ATR) infrared spectroscopy was designed, built, and tested. This instrument provides a measurement sensitivity much greater (by a factor of 6 for SO4²⁻) than that obtainable using the KBr-pellet method. This instrument collects size- and time-resolved samples and is potentially capable of providing automated, near real-time aerosol analysis. Exploratory work on a novel approach to the determination of proton acidity in filter- or impactor-collected aerosol samples is also described. In this technique, the acidic sample is reacted with an access of a tagged, vapor-phase base. The unreacted base is flushed off and the amount of the tag retained by the sample is a direct measure of the proton acidity of the sample. The base was tagged with germanium, which can be conveniently determined by the x-ray fluorescence technique.
ANL/HIWAY: an Air Pollution Evaluation Model for Roadways
This report describes a computer program, called ANL/HIWAY, for estimating air quality levels of nonreactive pollutants produced by vehicular sources. It is valid for receptors at distances of tens to hundreds of meters, at an angle, downwind of the roadway, in relatively uncomplicated terrain. It may be used by planners to analyze the effects of a proposed roadway on adjacent air quality. The ANL/HIWAY model expands the evaluation capabilities of the EPA/HIWAY dispersion model. This report also serves as a user's manual for running the ANL/HIWAY PROGRAM. All command structures are described in detail, with sample problems exemplifying their use.
ANL/HTP: A Computer Code for the Simulation of Heat Pipe Operation
ANL/HTP is a computer code for the simulation of heat pipe operation, to predict heat pipe performance and temperature distributions during steady state operation. Source and sink temperatures and heat transfer coefficients can be set as input boundary conditions, and varied for parametric studies. Five code options are included to calculate performance for fixed operating conditions, or to vary any one of the four boundary conditions to determine the heat pipe limited performance. The performance limits included are viscous, sonic, entrainment capillary, and boiling, using the best available theories to model these effects. The code has built-in models for a number of wick configurations - open grooves, screen-covered grooves, screen-wrap, and arteries, with provision for expansion. The current version of the code includes the thermophysical properties of sodium as the working fluid in an expandable subroutine. The code-calculated performance agrees quite well with measured experiment data.
ANL Technical Support Program for DOE Environmental Restoration and Waste Management
A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report for October 1991 - September 1992
Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report October 1990 - September 1991
A program has been established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are likely to affect waste glass reaction during repository disposal, with emphasis on an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report October 1993 - September 1994
A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
Annex to 7-GeV Advanced Photon Source : Conceptual Design Report
The Annex to the 7-GeV Advanced Photon Source Conceptual Design Report updates the Conceptual Design Report of 1987 (CDR-87) to include the results of further optimization and changes of the design during the past year. The design changes can be summarized as affecting three areas: the accelerator system, conventional facilities, and experimental systems. Most of the changes in the accelerator system result from inclusion of a positron accumulator ring (PAR), which was added at the suggestion of the 1987 DOE Review Committee, to speed up the filling rate of the storage ring. The addition of the PAR necessitates many minor changes in the linac system, the injector synchrotron, and the low-energy beam transport lines. 63 figs., 18 tabs.
Annual Report for 1963: Metallurgy Division
Report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963. Annual experiments, programs, and studies are presented. This report includes tables, illustrations, and photographs.
Annual Research Summary
Report on activities of the Division of Biological and Medical Research in carcinogenesis, low level radiation, molecular biology, and toxicology.
Annual Site Environmental Report for Argonne National Laboratory
Report on the environmental impact of Argonne National Laboratory.
Annual Technical Report
Highlights of the Chemical Technology Division's activities during 1990, including electrochemical technology and advanced batteries and fuel cells, technology for coal-fired magnetohydrodynamics and fluidized-bed combustion, methods for recovery of energy from municipal waste, and techniques for treatment of hazardous organic waste, the reaction of nuclear waste glass and spent fuel under conditions expected for a high-level waste repository.
Annual Technical Report
Highlights of the Chemical Technology (CMT) Division's activities during 1989 are presented. In this period, CMT conducted research and development in the following areas: (1) electrochemical technology, including high-performance batteries (mainly lithium/iron sulfide and sodium/metal chloride), aqueous batteries (lead-acid and nickel/iron), and advanced fuel cells with molten carbonate and solid oxide electrolytes; (2) coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology for fluidized-bed combustion; (3) method, for recovery of energy from municipal waste and techniques for treatment of hazardous organic waste; (4) nuclear technology related to a process for separating and recovering transuranic elements from nuclear waste and for producing 99Mo from low-enriched uranium targets, the recovery processes for discharged fuel and the uranium blanket in a sodium-cooled fast reactor (the Integral Fast Reactor), and waste management; and (5) physical chemistry of selected materials in environments simulating those of fission and fusion energy systems.
Annual Technical Report
Report of Argonne Chemical Technology division activities, including high-performance batteries, aqueous batteries, advanced fuel cells, and coal utilization.
Annual Technical Report 1980
Report of activities of Argonne Chemical Engineering Division, including advanced battery project, electro-chemical project management, advanced fuel cell development, utilization of coal, magnetohydrodynamics heat and seed recovery technology, solar energy, fast reactor chemistry research, nuclear fuel cycle studies, magnetic fusion energy research, and basic energy science.
Apparatus for Testing Smooth and Ribbed Tubing with Pulsed Eddy Currents
Report of the test results of a pulsed eddy-current apparatus for inspecting the integrity of smooth and ribbed tubing as well as discussion of transducer and preamplifier features, scanning procedures, and theory of operation.
Application of a Multigrid Method to a Buoyancy-Induced Flow Problem
The numerical prediction of buoyancy-induced flows provides special difficulties for standard numerical techniques associated with velocity-buoyancy coupling. We present a multigrid algorithm based upon a novel relaxation scheme that handles this coupling correctly. Numerical experiments have been performed that show that this approach is reasonably efficient and robust for a range of Rayleigh numbers and a variety of cycling strategies.
The Application of Automated Reasoning to Proof Translation and to Finding Proofs with Specified Properties: a Case Study in Many-Valued Sentential Calculus
In both mathematics and logic, many theorems exist such that each can be proved in entirely different ways. For a striking example, there exist theorems from group theory that can be proved by relying solely on equality and (from the viewpoint of automated reasoning) the use of paramodulation, but can also be proved in a notation in which equality is totally absent and the inference rule is condensed detachment (captured with a single clause and the rule hyper-resolution). A study of such examples immediately shows how far from obvious is the problem of producing a proof in one system even in the presence of a proof in another; such problems can be viewed as ones of translation, where the rules of translation and the translation itself are frequently difficult to obtain. In this report, we discuss in detail various techniques that can be applied by the automated reasoning program OTTER to address the translation problem to obtain a proof in one notation and inference system given a proof in a completely different notation and inference system. To illustrate the techniques, we present a full treatment culminating in a successful translation'' of a proof of a theorem from many-valued sentential calculus. To our delight and amazement, instead of the expected translation consisting of approximately 175 applications of condensed detachment, OTTER obtained a far shorter proof. We also touch on techniques for finding shorter proofs and techniques for finding proofs satisfying some given property.
Application of Electron-Bombardment Heating for Boiling Liquid Metals
Report discussing the "problem of obtaining a curve of the heat flux vs. temperature difference for boiling liquid metals" (p. 3). Contains discussions of a variety of heating techniques, though it focuses on electron-bombardment heating.
Application of Frequency-Modified Life Approach to the Low-Cycle Fatigue Behavior of Type 304 Stainless Steel
The application of the frequency-modified life equation to fatigue life prediction has been critically examined using the extensive fatigue data generated for Type 304 stainless steel at 1100 degrees F under a variety of cyclic-loading conditions. The parameters that enter into the frequency-modified life equation vary with strain rate and show a transition coinciding with the frequency of cycling at which a change in the fracture appearance from predominantly transgranular to predominantly intergranular failure mode or vice versa occurs. The accuracy in life prediction is improved when the effect of strain rate on life-predictive parameters is considered. It is shown how the effect of compressive and symmetric hold time on fatigue life can be taken into account. A comparison between the frequency-modified life approach of Coffin and the damage-rate approach recently developed by Majumdar and Maiya is also made to show the importance of wave-shape on low-cycle fatigue life.
Application of International Safeguards to Fast Critical Assembly Facilities. FY 1980 Summary Report
Nuclear materials inventory-verification techniques for large split-table fast critical assemblies are being studied in this program. Emphasis has been given to techniques that minimize fuel handling in order to reduce facility downtime and radiation exposure to the inventory team. The techniques studied include drawer seals, autoradiography, and spectral index measurements. Two-drawer sealing techniques have been studied, and the relative strengths and weaknesses are pointed out. The rod-type locking mechanism would not disrupt the reactor cooling air flow or interfere with autoradiography but is more expensive to implement. Passive autoradiography was used in a ZPPR inventory to verify to a 93% confidence level that less than 8-kg plutonium was missing. The inventory was completed in four days by a five-member team with radiation exposures well within acceptable limits. Two autoradiographic film packages were developed to distinguish HEU from a DU matrix. The 30-mil pack requires an exposure between 4 and 16 hours and fits into most of the drawers. The 40-mil pack requires only a two-hour exposure but fits into less than half the drawers.
The Application of Neutron-Activation Analysis to the Determination of Leach Rates of Simulated Nuclear-Waste Forms
The application of neutron activation analysis to the determination of element release from simulated nuclear waste forms during leaching is described for several different glasses. Potential neutron irradiation effects are discussed, and it is shown, by a series of leach tests on activated and non-activated glass samples, that neutron irradiation has no discernible effect on the release of silicon and cesium during leaching. The radioisotopes best suited for analysis with this method and their associated detection limits are identified, and the method's applicability to waste forms other than glass is discussed.
Application of NMR Spectroscopy and Multidimensional Imaging to the Gelcasting Process and in-situ Real-Time Monitoring of Cross-Linking Polyacrylamide Gels
In the gelcasting process, a slurry of ceramic powder in a solution of organic monomers is cast in a mold. The process is different from injection molding in that it separates mold-filling from setting during conversion of the ceramic slurry to a formed green part. In this work, NMR spectroscopy and imaging have been conducted for in-situ monitoring of the gelation process and for mapping the polymerization. ¹H nuclear magnetic resonance spectra have been obtained during polymerization of a premix of soluble reactive methacrylamide (monomer) and N, N'-methylene bisacrylamide (cross-linking molecules). The premix was polymerized by adding ammonium persulfate (initiator) and tetramethyl-ethylene-diamine (accelerator) to form long-chain, cross-linked polymers. The time-varying spin-lattice relaxation times T₁ during polymerization have been studied at 25 and 35 C, and the variation of spectra and T₁ with respect to extent of polymerization has been determined. To verify homogeneous polymerization, multidimensional NMR imaging was utilized for in-situ monitoring of the process. The intensities from the images are modeled and the correspondence shows a direct extraction of T₁ data from the images.
Application of the NNWSI [Nevada Nuclear Waste Storage Investigations] Unsaturated Test Method to Actinide Doped SRL [Savannah River Laboratory] 165 Type Glass
The results of tests done using the Unsaturated Test Method are presented. These tests, done to determine the suitability of glass in a potential high-level waste repository as developed by the Nevada Nuclear Waste Storage Investigations Project, simulate conditions anticipated for the post-containment phase of the repository when only limited contact between the waste form and water is expected. The reaction of glass occurs via processes that are initiated due to glass/water vapor and glass/liquid water contact. Vapor interaction results in the initiation of an exchange process between water and the more mobile species (alkalis and boron) in the glass. The liquid reaction produces interactions similar to those seen in standard leaching tests, except due to the limited amount of water present and the presence of partially sensitized 304L stainless steel, the formation of reaction products greatly exceeds that found in MCC-1 type leach tests. The effect of sensitized stainless steel on the reaction is to enhance breakdown of the glass matrix thereby increasing the release of the transuranic elements from the glass. However, most of the plutonium and americium released is entrained by either the metal components of the test or by the reaction phases, and is not released to solution.
Application of the Pulsed-Neutron Activation Technique for Flow Measurements at EBR-II
This report describes the pulsed-neutron-activation (PNA) flow-measuring technique as applied to in situ fluid-flow measurement at EBR-II. Analytic relationships are derived for modeling the process and estimating the uncertainty in measurement. Results from measurements of both water flow and secondary-sodium flow are presented. Results from PNA measurements of water side of the EBR-II steam system have led better definition of plant parameters. Results from sodium-flow measurements are used to provide a correlation for in situ calibration of the electromagnetic sodium flowmeter in the secondary system.
Applied Mathematical Sciences Research at Argonne April 1, 1980-March 31, 1981
This report reviews the research activities of the Applied Mathematical Sciences Section for the period April 1, 1980, through March 31, 1981. The body of the report discusses various projects carried out in three major areas of research: applied analysis, computational mathematics, and software engineering. Information on section staff, visitors, workshops, and seminars is found in the appendices.
Applied Mathematical Sciences Research at Argonne, April 1, 1981-March 31, 1982
This report reviews the research activities in Applied Mathematical Sciences at Argonne National Laboratory for the period April 1, 1981, through March 31, 1982. The body of the report discusses various projects carried out in three major areas of research: applied analysis, computational mathematics, and software engineering. Information on section staff, visitors, workshops, and seminars is found in the appendices.