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- Inelastic-Collision Cross Sections for Ne
- Cross sections for inelastic collisions of slow electrons and the dipole oscillator-strength distribution for the neon atom are given in tabular form. The results are based on experimental data that were checked and adjusted for internal consistency.
- Predicted Heat-Transfer Performance of an Evacuated Glass-Jacketed CPC Receiver : Countercurrent Flow Design
- The heat-transfer performance of an evacuated glass-jacketed CPC-receiver facility, free on one end and fixed onto the glass jacket at the other, was carried out using heat-transfer relationships and the best information available in the literature. Specifically, the collector examined was a 3x-CPC facility, 8 ft long, with an entrance aperture 4.5 in. wide covered with a single glass cover, and provided with an aluminum reflecting surface (rho = 0.88). To maximize heat retention, a selectively treated receiver surface, epsilon = 0.11, was used. The optical efficiency of this CPC collector facility was calculated to be eta₀ = 0.536.
- The Atomic Spectrum of Neptunium
- A description and interpretation of the atomic spectrum of neptunium are given. Wavelengths were measured for 6096 spectrum lines in the range 3793 to 38,812 cm⁻¹ (26,353 to 2575 A), of which 2526 were classified as transitions between 329 odd levels and 130 even levels of neutral neptunium (Np I). The data are presented in five tables.
- Environmental Pollutants and the Urban Economy : Phase 1. Final Report, June 1972-October 1975
- Costs and benefits of various urban air pollution control policies have been examined in Phase 1 of the Environmental Pollutants and the Urban Economy study being conducted jointly by Argonne National Laboratory and the University of Chicago. The need for sound economic evaluation of air quality regulations is evidenced by the resistance of many industries to pollution control policies based solely on the technical feasibility of achieving public health-related standards. For many firms that emit air pollutants, the cost of not complying with some regulations is significantly less than the cost of compliance. This final report on the Phase 1 research presents highlights of what has been learned, the mechanisms developed for transferring results to users, a bibliography of documents produced during the project, and a collection of correspondence, articles, and evaluation illuminating the use of project work by others.
- Class Notes for a PL/I Course
- Presented here are notes for a course in PL/I. They might serve as a guide to those who are developing a course, or as class notes for that course. They might be useful as a textbook independent of any course; as such a textbook, however, they are not self-contained because of the built-in assumption that they will supplement lectures and be accompanied by manuals. Very nearly the full language is taught here, with the emphasis on concepts rather than practical details. Discussion of I/O is avoided until roughly the midpoint of the course. The hoped-for consequence for students is an enhanced perception and understanding of the many concepts and their logical relationships. The dawning of the age of transportability for PL/I programs gives the user a reason, for the first time, to avoid convenient but illegal language.
- Development and Demonstration of Compound Parabolic Concentrators for Solar Thermal Power Generation and Heating and Cooling Applications, Progress Report: July-December 1975
- Progress report describing the development of Compound Parabolic Concentrators (CPC). A tenfold concentrator with a cavity receiver was constructed and tested. The optical efficiency was very good (65 percent), but the thermal performance was degraded by heat losses of the cavity receiver. A summary of the results of subcontracts described in the previous progress report are presented, and the influence of these results on ANL programs is noted.
- Physics of Reactor Safety, Quarterly Report: January-March 1976
- Quarterly progress report summarizing work done in Argonne National Laboratory's Applied Physics Division on reactor safety research and technical coordination of the RSR safety analysis program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and planning of DEMO safety-related critical experiments by members of the Zero Power Reactor (ZPR) Planning and Experiments Group.
- Biaxial Creep Behavior of Ribbed GCFR Cladding at 650 degrees C in Nominally Pure Helium (99. 99%)
- Biaxial creep-rupture tests were conducted on 12 prototypic GCFR fuel-cladding specimens at 650 deg C and a nominal hoop stress of 241.3 MPa. All test specimens were fabricated from 20% cold-worked Type 316 stainless steel tubes that were ribbed on the outer surface by mechanical grinding or electro-chemical etching. Test variables included specimen length and the presence or absence of weld-reinforcing end collars.
- Proceedings of the Symposium and Workshop on Advanced Battery Research and Design : March 22-24, 1976
- The idea for this meeting evolved from interest expressed by members of the Chicago Section of the Electrochemical Society in convening a symposium on the development of high-energy secondary batteries. The relevance of this subject is evidenced by the several research programs that have been initiated recently in the United States and Europe to develop advanced batteries for use as energy storage devices on electric utility networks and as power sources for electric automobiles.
- Photoexcitation in Superconductors
- Dissertation discussing the results of experiments to study the behavior of superconductors under light illumination.
- High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: July-December 1975
- Progress report describing the research and management efforts of Argonne National Laboratory's program on high-performance lithium/metal sulfide batteries during the period July-December 1975. The batteries are being developed for two applications: off-peak energy storage in electric utility networks and electric-vehicle propulsion. The battery designs for the two applications differ, particularly in cell configuration and electrode design because of the differing performance requirements.
- PTOLEMY, a Program for Heavy-Ion Direction-Reaction Calculations
- Ptolemy is an IBM/360 program for the computation of nuclear elastic and direct-reaction cross sections. It carries out both optical-model fits to elastic-scattering data at one or more energies, and DWBA calculations for nucleon-transfer reactions. Ptolemy has been specifically designed for heavy-ion calculations. It is fast and does not require large amounts of core. The input is exceptionally flexible and easy to use. This report outlines the types of calculation that Ptolemy can carry out, summarizes the formulas used, and gives a detailed description of its input.
- PTOLEMY : a Program for Heavy-Ion Direction-Reaction Calculations
- Many important additions and improvements have been made to Ptolemy since the previously-documented version of February 1976. An indication of this is that the list of keywords has been expanded by thirty. Collective-model inelastic excitement has been added. The computation of the transfer DWBA amplitudes has been significantly improved by the use of interpolation in the Ri +Ro variable. Elastic scattering and reactions involving identical particles may now be computed. Simultaneous optical model fits to several different elastic channels are possible. Significant changes to this manual are marked with a vertical bar in the left margin and should be carefully reviewed. In addition the contents of the manual have been extensively re-ordered.
- Coal Supply and Air Quality Limitations on Fossil-Fueled Energy Centers
- The coterminous United States is screened on a county-by-county basis to identify areas most likely to provide sites for fossil energy centers (FECs) utilizing local coals and having capacities between 5,000 and 20,000 MWe. Areas eliminated as potential sites include national public lands excluded by legislation, urbanized areas, Air Quality Maintenance Areas for particulates and SO2, and counties where air quality data indicate violations of particulate or SO2 ambient standards. The remaining counties are further screened for suitable coal reserves. The quality of coal required for an FEC to meet emissions and ambient standards is determined for sulfur content and heating value. Based on Bureau of Mines coal reserve data, counties in areas with not enough quality reserves to support an FEC are eliminated. Areas most likely to provide sites for FECs of 5,000, 10,000, and 20,000 MWe, in two different spatial configurations, each with and without flue gas desulfurization are determined and mapped. The possible impacts of regulations for the prevention of significant deterioration are illustrated.
- Cost Estimate for the Commercial Manufacture of Lithium/Iron Sulfide Cells for Load-Leveling
- An estimate was made of the cost of commercial manufacture of batteries for load-leveling in utility networks, based on the lithium-aluminum/iron sulfide system. The battery design chosen is the 0.92-kWh cell proposed for the BEST Facility. The manufacturing plant was sized to produce 5000 of such cells per day. These cells are assembled for sale in battery cases or sub-modules, 24 cells to a case. The plant investment is estimated to be $12,500,000. A selling price of $29.16 per kWh is projected; this price yields a 25 percent return on invested capital. An allowance for recycle lithium yields a net price of $27.33 per kWh.
- Physics of Reactor Safety, Quarterly Report: October-December 1975
- Quarterly progress report summarizing work done in Argonne National Laboratory's Applied Physics Division including: reactor safety research and technical coordination of the RSR safety analysis program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and planning of DEMO safety-related critical experiments by members of the Zero Power Reactor (ZPR) Planning and Experiments Group.
- SYNBURN : a Fast-Reactor Fuel-Cycle Program
- The SYNBURN computer program for fast reactors will calculate all the neutronics necessary to completely characterize the equilibrium cycle as well as the startup to equilibrium cycles. The program's run time is very short and this makes the program suitable for survey of parametric studies. It can search on the cycle time for a specified burnup, for the shim control necessary for criticality as well as feed enrichments and the enrichment ratio among core zones. SYNBURN synthesizes in a very simple fashion the one-dimensional fluxes in radial and axial geometry to achieve an approximate two-dimensional solution which agrees very well with the exact two-dimensional solution when measuring regional integrated quantities.
- 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.
- Light-Water-Reactor Safety Research Program, Quarterly Progress Report: October-December 1975
- Quarterly report summarizing work by Argonne National Laboratory on water-reactor-safety heat-transfer and flow problems. "The following research and development areas are covered: (1) Loss-of-coolant Accident Research: Heat Transfer and Fluid Dynamics; (2) Transient Fuel Response and Fission-product Release Program; and (3) Mechanical Properties of Zircaloy Containing Oxygen" (p. x).
- The Environmental Costs of Landfills and Incinerators
- After an introductory statement describing the characteristics of landfills and incinerators, these two devices for municipal waste disposal are compared in terms of economic and environmental costs. Cost data for the Chicago area is used. It is concluded that landfills have lower investment, operating and environmental costs.
- Final Summary Report of Fuel-Dynamics Tests H2 and E4
- Results of two failure experiments using LMFBR-type fuel during simulated unprotected transient overpower accidents are reported and analyzed. In both experiments, a single fresh fuel pin in a Mark0IIA loop was subjected to a temperature-limited, step-reactivity irradiation in the TREAT reactor. Total energy was 490 MJ in Test H2 and in Test E4.
- Noise Pollution from Expressways
- This paper provides an economic analysis of three noise abatement strategies designed to interrupt the path of noise between highways and residential areas, and makes some abatement policy suggestions.
- Computer-Code Formulation for Three-Dimensional HEXCAN Response Coupled with Internal Hydrodynamics
- A procedure is described for the dynamic analysis of a fast-reactor hexagonal subassembly. The internals of the fuel subassembly are treated by an axisymmetric hydrodynamic code REXCO-HT which, among other properties, possesses a model of an MFCI pressure source. The housing of the fuel subassembly is handled by the SADCAT code, which is based on a triangular finite element in three-dimensional space. The code is used to illustrate the discrepancies involved if the hexcan is modeled by a cylinder of the same thickness. A study is also made of the reduction of cylinder thickness such that the same final cylindrical deformation can be predicted. A discussion in arriving at such an equivalence is offered.
- 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.
- Simulation Test Approach to the Evaluation and Comparison of Unconstrained Nonlinear Optimization Algorithms
- A simulation test technique was developed to evaluate and compare unconstrained nonlinear optimization computer algorithms. Descriptions of the test technique, test problems, computer algorithms tested, and test results are provided.
- SYN3D: a Single-Channel, Spatial Flux Synthesis Code for Diffusion Theory Calculations
- This report is a user's manual for SYN3D, a computer code which uses single-channel, spatial flux synthesis to calculate approximate solutions to two- and three-dimensional, finite-difference, multi-group neutron diffusion theory equations. SYN3D is designed to run in conjunction with any one of several one- and two-dimensional, finite-difference codes (required to generate the synthesis expansion functions) currently being used in the fast reactor community. The report describes the theory and equations, the use of the code, and the implementation on the IBM 370/195 and CDC 7600 of the version of SYN3D available through the Argonne Code Center.
- Materials Science Division Coal Technology Quarterly Report: October-December 1975
- Quarterly report of the Argonne National Laboratory Materials Science Division regarding coal technology research and development.
- Urban Design and Public Exposure to Carbon Monoxide
- In protecting the public from the risk of exposure to damaging levels of carbon monoxide, two approaches are possible; the pollutant's concentration may be lowered by traffic management measures or the public's rate of exposure may be reduced through urban design features. The present emphasis on traffic management stresses improving the flow and reducing the level of traffic, goals that are extremely costly to achieve in downtown areas. This paper examines ways to reduce risk of exposure by the physical design of new downtown residential developments. The concept is not a novel one, having been successfully implemented in industry to provide occupational health and safety.
- Study on Flow Instabilities in Two-Phase Mixtures
- Various mechanisms that can induce flow instabilities in two-phase flow systems are reviewed and their relative importance discussed. In view of their practical importance, the density-wave instabilities have been analyzed in detail based on the one-dimensional two-phase flow formulation. The dynamic response of the system to the inlet flow perturbations has been derived from the model; thus the characteristic equation that predicts the onset of instabilities has been obtained. The effects of various system parameters, such as the heat flux, sub-cooling, pressure, inlet velocity, inlet orificing, and exit orificing on the stability boundary have been analyzed. In addition to numerical solutions, some simple stability criteria under particular conditions have been obtained. Both results have been compared with various experimental data, and a satisfactory agreement has been demonstrated.
- Explosive Interaction of Molten UO2 and Liquid Sodium
- The interim report presented describes a continuation of the work reported in ANL-7890, Interaction of Sodium with Molten Uranium dioxide and Stainless Steel Using a Dropping Mode of Contact. In the current study, sodium was injected into a pool of molten uranium dioxide. The experiment consistently produced vapor explosions, both with the injection nozzle above and beneath the surface of the uranium dioxide. Although the efficiency of the conversion of thermal to mechanical energy was small (due in part to very conservative data analysis and an inefficient geometry), the results did demonstrate that there is no intrinsic reason why reactor materials cannot produce a vapor explosion.
- Effects of Possible Compression Loading of EBR-II Subassemblies Due to Irradiation-Induced Swelling and Changes in Reactor Environment
- A condition of compression loading could possibly occur to a subassembly as a result of large length changes to irradiation-induced swelling and thermal expansion. The effects of axial compression loading on EBR-II experimental and driver-fuel subassemblies were evaluated. Compression tests that were performed on the slotted top fixture of a subassembly showed that a force of 2100 lb at 900 degrees F would close the slot enough so that the core-gripper blade would not fit into the slot. Such a slot closure would prevent the subassembly from being removed from the reactor with the core gripper.
- Xenon-Tagging in Production of EBR-II Mark II Driven-Fuel Elements
- About 1200 Mark II driver-fuel elements were xenon-tagged to facilitate qualification for irradiation of Mark II fuel manufactured at ANL-West. Tagging equipment was designed and developed. In this equipment, the plenum in a fuel-element jacket was evacuated then filled with xenon to a predetermined pressure. The equipment design allows tagging and element fabrication to proceed normal rates for production of fuel elements. A Kr-85 tracer in the xenon-tag gas verified by gamma counting the adequate tagging of each element.
- Investigation of Reactivity Anomalies in EBR-II
- A data-collection and advisory team was formed to investigate observations of power reactivity decrement (PRD) and reactivity loss rate (RLR) obtained during EBR-II reactor run 74, because both the PRD and RLR were judged to be high during that run. This report describes the efforts to develop a realistic model explaining the reactivity observations for run 74 and presents recommendations for additional diagnostic information in the event of a recurrence of off-normal behavior of reactivity.
- U-Pu-Zr Metal Alloy: a Potential Fuel for LMFBR's
- This report critically reviews the available information pertinent to the potential use of uranium-plutonium-zirconium alloy fuels clad with stainless steel in LMFBR's. The areas considered include breeding potential, burnup potential, thermal performance, fuel fabricability, fuel reprocessing, and safety considerations. Because information on uranium-plutonium-zirconium alloys is limited, wide use is made of experience with EBR-II metallic driver fuel to infer advantages and limitations of uranium-plutonium-zirconium fuels. It is concluded that sufficient potential exists for the applicability of uranium-plutonium-zirconium fuels to LMBFR's to warrant additional analytical and experimental studies.
- Environmental Monitoring at Argonne National Laboratory, Annual Report: 1975
- Annual report of the environmental monitoring program at Argonne National Laboratory, discussing activities and findings of the group.
- Plutonium Safety Training Course
- This course seeks to achieve two objectives: to provide initial safety training for people just beginning work with plutonium, and to serve as a review and reference source for those already engaged in such work. Numerous references have been included to provide information sources for those wishing to pursue certain topics more fully. The first part of the course content deals with the general safety approach used in dealing with hazardous materials. Following is a discussion of the four properties of plutonium that lead to potential hazards: radioactivity, toxicity, nuclear properties, and spontaneous ignition. Next, the various hazards arising from these properties are treated. The relative hazards of both internal and external radiation sources are discussed, as well as the specific hazards when plutonium is the source. Similarly, the general hazards involved in a criticality, fire, or explosion are treated. Comments are made concerning the specific hazards when plutonium is involved. A brief summary comparison between the hazards of the trans-plutonium nuclides relative to plutonium-239 follows. The final portion deals with control procedures with respect to contamination, internal and external exposure, nuclear safety, and fire protection. The philosophy and approach to emergency planning are also discussed.
- Final Safety Analysis Addenda to Hazards Summary Report, Experimental Breeder Reactor II (EBR-II) : Upgrading of Plant Protection System, Volume 1
- This report is a compilation of the formal Final Safety Analysis Addenda (FSAA's) to the EBR-II Hazard Summary Report and Addendum that have been prepared in support of certain modifications to the reactor-shutdown-system portion of the EBR-II plant protection system. Each major section is an edited version of the original FSAA for a particular modification and provides a description of the pre - and post -modification system, the rationale for the modification, and required supporting safety analysis.
- High-Performance Batteries for Off-Peak Energy Storage and Electric-Vehicle Propulsion, Progress Report: January-March 1976
- Quarterly report describing the research and management effort of Argonne National Laboratory's program on lithium/metal sulfide batteries during the period January-March 1976. These batteries are being developed for energy storage on utility networks and for electric-vehicle propulsion. The present cells are vertically oriented, piismatic cells with a central positive electrode of FeS or FeS; and two facing negative electrodes of lithium-aluminum alloy, and an electrolyte of molten LiCl-KC1. The cell operating temperature is 400-450C.
- Experimental Study of the Neutronics of the First Gas Cooled Fast Reactor Benchmark Assembly (GCFR Phase 1 Assembly)
- The Gas Cooled Fast Reactor (GCFR) Phase I Assembly is the first in a series of ZPR-9 critical assemblies designed to provide a reference set of reactor physics measurements in support of the 300 MW(e) GCFR Demonstration Plant designed by General Atomic Company. The Phase I Assembly was the first complete mockup of a GCFR core ever built. A set of basic reactor physics measurements were performed in the assembly to characterize the neutronics of the assembly and assess the impact of the neutron streaming on the various integral parameters. The analysis of the experiments was carried out using ENDF/B-IV based data and two-dimensional diffusion theory methods. The Benoist method of using directional diffusion coefficients was used to treat the anisotropic effects of neutron streaming within the framework of diffusion theory. Calculated predictions of most integral parameters in the GCFR showed the same kinds of agreements with experiment as in earlier LMFBR assemblies.
- One-Dimensional Cladding-Relocation Model for Fast-Reactor Loss-of-Flow Accidents
- The motion and location of the molten-cladding during an unprotected loss-of-flow accident in liquid metal fast breeder reactors are important because of the effects on the reactivity and the subsequent fuel motion. The present study analyzes the cladding-relocation problem based on a single-channel film-flow model and a simple thermal transient model for fuel pins. The motion of molten cladding induced by sodium-vapor streaming undergoes initial rapid upward acceleration, slowing down, flow reversal, and eventual slumping down into liquid sodium at the lower end of the heated section. Freezing of the molten cladding at the unheated upper plenum region is possible; bottom freezing and blockage formation were also included in the analysis. A simple calculation has been made for the R-series seven-pin tests in the TREAT reactor. The agreement of the overall physical behavior of the cladding motion with the post-test observations is quite satisfactory.
- 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.
- Simple Conduction Model with Phase Change for Fuel Pin
- A simple conduction model with phase change has been developed for the transient analysis of a fuel pin based on average properties and lumped-parameter techniques. The transient behavior of fuel and cladding can be accurately described by simple analytical expressions that agree with conventional numerical approaches for under-cooling transient analysis. If it be assumed that the heat-transfer resistance between the fuel and cladding remains the same for both steady-state and transient periods, the phase-change problem for fuel and cladding melting can be significantly simplified. BY using the predetermined average overall heat-transfer coefficient across a fuel pin in the steady-state period, the average transient fuel and cladding temperatures can be formulated analytically. For loss of flow at constant power, the start of melting and complete melting for both the fuel and cladding can be estimated with considerable accuracy.
- Risk-assessment methodology for fast breeder reactors
- The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly with respect to their applicability for risk assessment of future commercial fast breeder reactors. All methods are based on the calculation of accident consequences for relatively few accident scenarios. The role and general impact of uncertainties in fast-reactor accident analysis are discussed. The discussion shows the need for improvement of the methodology. A generalized and improved risk-assessment methodology is outlined and proposed (accident-spectra-progression approach). The generalization consists primarily of an explicit treatment of uncertainties throughout the accident progression. The results of this method are obtained in form of consequence distributions. The width and shape of the distributions depend in part on the superposition of the uncertainties. The first moment of the consequence distribution gives an improved prediction of the ''average'' consequence. The higher-consequence moments can be used for consideration of risk aversion. The assessment of the risk of one or a certain number of nuclear reactors can only provide an ''isolated'' risk assessment. The general problem of safety risk assessment and its relation to public acceptance of certain modes of power production is a much broader problem area, which is also discussed.
- 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.
- Experimental and Analytical Study of the Sputtering Phenomena
- An experimental apparatus was constructed to examine the heat-transfer characteristics of a sputtering front. In the present study, a heat source of sufficient intensity was located immediately below the sputtering front, which prevented its downward progress, thus permitting detailed measurements of steady-state surface temperatures throughout a sputtering front. A two-dimensional analytical model was developed to describe a stationary sputtering front where the wet-dry interface corresponds to a CHF phenomena and the dry zone is adiabatic. This model is nonlinear because of the temperature dependence of the heat-transfer coefficient in the wetted region and has yielded good agreement with data. A simplified one-dimensional approximation was developed which adequately describes these data. Finally, by means of a coordinate transformation and additional simplifying assumptions, this analysis was extended to analyze moving sputtering fronts, and reasonably good agreement with reported data was shown.
- Reactor Physics Studies in the Engineering Mockup Critical Assembly of the Fast Test Reactor
- Reactor physics studies in the Engineering Mockup Critical (EMC) assembly of the Fast Test Reactor (FTR) facility are reported. The study included measurements of the neutron spectrum, Doppler effect, sodium-void worth, reaction rates, subassembly worths, material replacement worths, and FTR control, safety and shim rod worths. Each of these physics studies were made in a clean plutonium (low-Pu-240) fuel composition environment and a dirty plutonium (high-Pu-240) fuel composition environment. The fuel studies were in support of determining the attendant effects of operation and safety of utilizing Light Water Reactor (LWR) plutonium fuel in the FTR. Comparison of the measured and calculated results are presented.
- Land Reclamation Program, Annual Report: July 1975-July 1976
- Annual report of the Argonne National Laboratory Land Reclamation Program outlining the activities and research conducted during the year, various assessments and discussion, and related documentation.
- Use of Krypton-85 for the Detection of Pinhole Failures in GCFR Cladding
- Radioactive krypton-85 is used as a tracer to detect pinhole failures in GCFR cladding. High-purity helium (99.99% pure) that contains 0.3 ppm krypton-85 is used to pressurize the tubular test specimens, and a Geiger-Mueller counter is used to detect the krypton-85 in the helium environmental gas as it leaves the test chamber. Under the least favorable conditions of temperature and specimen pressure, it is estimated that the smallest pinhole failure that could be detected within 60 sec would have an orifice diameter of 0.0102 cm. Using lead shielding around the Geiger-Muller counter to reduce background radiation, the electronics associated with the krypton-85 detector will terminate a biaxial creep test at krypton-85 activity levels above 20 counts/minute.
- Examination and Evaluation of in-Reactor Fracture of Shroud Tubes in Mixed-Oxide Fuel Experiment X159
- During disassembly and subsequent visual examinations of X159 (a Mark A-19A type of subassembly containing mixed-oxide fuel), 11 of 19 shroud tubes were found fully or partially severed. Several of the capsules within their shroud tubes were distinctly kinked at axial locations near those at which the shroud tubes were severed. The examination also disclosed that the shroud-tube fractures occurred during reactor operations.
- Development of Lithium/Metal Sulfide Batteries at Argonne National Laboratory : Summary Report
- Overview of the battery program at Argonne National Laboratory being developed for use as energy storage devices for load-leveling on electric utilities and as power sources for electric automobiles.