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Air Pollution and the Siting of Fossil Fuel Power Plants

Description: 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.
Date: 1976
Creator: Fishelson, Gordon; Rausser, Gordon C. & Cohen, Alan S.

An Algebraic Theory of Program Specification and Correctness Using Symmetry Operations

Description: 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.
Date: March 1987
Creator: Gabriel, John R.

Alternative Fuel Cycle Options : Performance Characteristics and Impact on Nuclear Power Growth Potential

Description: 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.
Date: September 1977
Creator: Chang, Y. I.; Till, C. E.; Rudolph, R. R.; Deen, J. R. & King, M. J.

An Alternative Library Under 4. 2 BSD UNIX on a VAX 11/780

Description: 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.
Date: February 1986
Creator: Cody, William James

Alternatives for Conversion to Solid Interim Waste Forms of the Radioactive Liquid High-Level Wastes Stored at the Western New York Nuclear Service Center

Description: 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.
Date: August 1981
Creator: Vogler, S.; Trevorrow, L. E.; Ziegler, A. A. & Steindler, M. J.

Alternatives for Disposal of Raffinate from the TRUEX Process

Description: 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.
Date: December 1989
Creator: Trevorrow, L. E. & Vandegrift, G. F.

Analysis of a Cylindrical Shell Vibrating in a Cylindrical Fluid Region

Description: 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.
Date: August 1976
Creator: Chung, Ho; Mulcahy, T. M.; Turula, P. & Jendrzeczyk, J. A.

Analysis of an Internally Pressurized Prismatic Cell Can

Description: 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.
Date: April 1980
Creator: Majumdar, S.

Analysis of Cracked Core Spray Injection Line Piping from the Quad Cities Units 1 and 2 Boiling Water Reactors

Description: 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.
Date: December 1983
Creator: Diercks, D. R.

Analysis of EBR-II Low-Power Dosimetry Run 78C

Description: 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.
Date: December 1977
Creator: Franklin, F. C.; Ebersole, E. R. & Heinrich, R. R.

An Analysis of Factors Influencing the Reliability of Retrievable Storage Canisters for Containment of Solid High-Level Radioactive Waste

Description: 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.
Date: August 1976
Creator: Mecham, W. J.; Seefeldt, Waldemar B. & Steindler, M. J.

Analysis of Heat-Pipe Absorbers in Evacuated-Tube Solar Collectors

Description: 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.
Date: February 1986
Creator: Hull, John R.; Schertz, William W. & Allen, John W.

Analysis of Nonlinear Fluid Structure Interaction Transient in Fast Reactors

Description: 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.
Date: 1978
Creator: Yang, C. Y.

Analysis of Proposed Gamma-Ray Detection System for the Monitoring of Core Water Inventory in a Pressurized Water Reactor

Description: 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.
Date: December 1987
Creator: Markoff, Diane Melanie

An Analysis of the High-Temperature Particulate Collection Problem

Description: 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.
Date: October 1977
Creator: Razgaitis, Richard

Analysis of the October 5, 1979 Lithium Spill and Fire in the Lithium Processing Test Loop

Description: 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.
Date: December 1981
Creator: Maroni, V. A.

Analytical Electron Microscopy Characterization of Fernald soils. Annual Report, October 1993 - September 1994

Description: 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.
Date: March 1995
Creator: Buck, E. C.; Brown, N. R. & Dietz, N. L.

Analytical Electron Microscopy Characterization of Uranium-Contaminated Soils from the Fernald Site, FY1993 Report

Description: 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.
Date: October 1994
Creator: Buck, E. C.; Cunnane, J. C.; Brown, N. R. & Dietz, N. L.

Analytical Investigation of Certain Aspects of LMFBR Subassembly-Failure Propagation

Description: 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.
Date: February 1976
Creator: Marr, William W.; Wang, P. Y.; Misra, B.; Padilla, A. & Crawford, R. M.

Analytical Techniques for Ambient Sulfate Aerosols

Description: 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.
Date: June 1981
Creator: Johnson, S. A.; Graczyk, D. G.; Kumar, R. & Cunningham, P. T.