Oxidation of copper and electronic transport in thermally grown large-grain poly-crystals of non-stoichiometric copper oxides were studied at elevated temperatures. Thermogravimetric copper oxidation was studied in air and oxygen at temperatures between 350 and 100 C. From the temperature-dependence of oxidation rates, three different processes can be identified for the oxidation of copper: bulk diffusion, grain-boundary diffusion, and surface control with whisker growth; these occur at high, intermediate, and low temperatures, respectively. Electrical conductivity measurements as a function of temperature (350 - 1134 C) and pO2 (10(sup⁻⁸-1.0 atm) indicated intrinsic electronic conduction in CuO over the entire range of conditions. Electronic behavior of non-stoichiometric Cu(sub 2)O indicates that the charge defects are doubly ionized oxygen interstitials and holes. The calculated enthalpy of formation of oxygen ((Delta)H(sub O(sub 2))) and the hole conduction energy (E(sub H)) at constant composition for non-stoichiometric Cu2O are 2.0 (plus minus) 0.2 eV and 0.82 (plus minus) 0.02 eV, respectively.

The radioactive content of samples of rain, surface water, soil, plants, and material from the beds of surface waters (bottom silt) which were collected and analyzed during 1953 are given in this report. Samples were collected form the Laboratory site, at locations with 25 miles, and at places 100 miles from the Laboratory. Since Laboratory waste water is discharged into Sawmill Creek, water from the this stream was analyzed daily. Other samples were collected from the Laboratory site periodically, and collections from the off-site locations were made at approximately quarterly intervals. Most of the results were obtained by counting total alpha and beta activity; selected samples were analyzed for specific nuclides and elements. The total activity measurements provided a rapid means of determining general levels of radioactivity which could be compared between samples and indicated which samples should be analyzed in more detail. Radioactive contamination attributable to Laboratory operations was found only in water and bottom silt taken from Sawmill Creek below the outfall of Laboratory waste water (below site).

Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).

The PTA-1 code for computing pressure transients in piping networks includes a computational model to treat the significant effect of plastic deformation of the piping on pulse propagation. Stanford Research Institute has completed an experimental program on the response of piping systems to internal pressure pulses which plastically deform portions of the piping. This report makes extensive comparisons between PTA-1 computations and these experimental results. The excellent agreement obtained for both pressure histories and strain histories for all the experiments indicates that the PTA-1 computational model for pipe plasticity effects is accurate. The computation-experiment comparisons also permit a number of observations and conclusions to be made on other aspects of computational modeling of pressure transients, particularly with respect to pulse propagation around elbows.

A series of polymer-based extraction systems, based on the use of polyethylene glycols (PEGs) or polypropylene glycols (PPGs), was demonstrated to be capable of selective extraction and recovery of long-lived radionuclides, such as Tc-99 and I-129, from Hanford SY-101 tank waste, neutralized current acid waste, and single-shell tank waste simulants. During the extraction process, anionic species like TcO₄⁻ and I⁻ are selectively transferred to the less dense PEG-rich aqueous phase. The partition coefficients for a wide range of inorganic cations and anions, such as sodium, potassium, aluminum, nitrate, nitrite, and carbonate, are all less than one. The partition coefficients for pertechnetate ranged from 12 to 50, depending on the choice of waste simulant and temperature. The partition coefficient for iodide was about 5, while that of iodate was about 0.25. Irradiation of the PEG phase with gamma-ray doses up to 20 Mrad had no detectable effect on the partition coefficients. The most selective extraction systems examined were those based on PPGs, which exhibited separation factors in excess of 3000 between TcO₄⁻ and NO₃⁻/NO₂⁻. An advantage of the PPG-based system is minimization of secondary waste production. These studies also highlighted the need for exercising great care in extrapolating the partitioning behavior …

Several sections of Type 304 stainless steel head spray piping, 6.25 cm (2.5 in.) in diameter, from the Dresden Unit 2 Boiling Water Reactor were examined to determine the nature and causes of coolant leakages detected during hydrostatic tests. Extensive pitting was observed on the outside surface of the piping, and three cracks, all located at a helical stripe apparently rubbed onto the outer surface of the piping, were also noted. Metallographic examination revealed that the cracking had initiated at the outer surface of the pipe, and showed it to be transgranular and highly branched, characteristic of chloride stress corrosion cracking. The surface pitting also appeared to have been caused by chlorides. A scanning electron microprobe x-ray analysis of the corrosion product in the cracks confirmed the presence of chlorides and also indicated the presence of calcium.

This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

This report describes the design of a facility capable of the simultaneous testing of up to 50 high-temperature (400 to 500 C) lithium alloy/iron sulfide cells; this facility is located in the Chemical Engineering Division of Argonne National Laboratory (ANL). The emphasis will be on the lifetime testing of cells fabricated by ANL and industrial contractors to acquire statistical data on the performance of cells of various designs. A computer-based data-acquisition system processes the cell performance data generated from the cells on test. The terminals and part of the data-acquisition equipment are housed in an air-conditioned enclosure adjacent to the testing facility; the computer is located remotely.

The R3 was the first of the R-series fuel-element meltdown tests performed to support modeling and code development for analysis of hypothetical, whole-core accidents in LMFBRs. Test R3 served as a proof test for the subsequent R4-R8 sequence of seven-pin tests examining coolant, cladding, and fuel behavior under thermal and hydraulic conditions representative of a hypothetical loss-of-coolant (LOF) with failure to scram in FFTF.

The papers presented at the first annual workshop on ice storage for cooling applications by participants from the U.S. and Canada are summarized. Novel methods of preparing naturally frozen ice and storing it are described. Attention is given to technical and economic problems and related design considerations. Comparison is made with conventional air conditioning methods. Both industrial and residential applications are discussed with regard to cost.

Suspected fission-product releases from 18 subassemblies between April 1977 and May 1978 are presented. Post-irradiation examinations pm 15 of the suspect subassemblies confirmed that all contained one or more breached elements. Except for two untagged subassemblies, xenon tagging was the primary method of identification, although other methods were used where appropriate. Methods to monitor and identify fission product sources are discussed. Problems encountered elements on plant availability were minimal during this reporting period. From all evidence, cladding breaching on elements in EBR-II continues to be a benign process.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

The germanium-lithium argon scanning system (GLASS) was installed in EBR-II to monitor and analyze the gamma activity of the reactor cover gas and the reactor building air. GLASS has the capability to identify and measure 20 or more gamma peaks. Applied to the reactor cover gas, this capability has proven useful in identifying the source of fission-gas leakage from fuel elements. The gamma-peak data can clearly distinguish a carbide-fuel source from an oxide-fuel source and can often help distinguish and oxide-fuel source from a metallic-fuel source.

Quarterly report describing the research and management efforts of the program at Argonne National Laboratory (ANL) on lithium/metal sulfide batteries during the period April-June 1976. These batteries are being developed for energy storage on utility networks and for electric-vehicle propulsion. The present cells, which operate at 400-4503C, are vertically oriented, prismatic cells with a central positive electrode of FeS or FeS2, two facing negative electrodes of lithium-aluminum alloy, and an electrolyte of molten LiCl-KCl.

Quarterly progress report discussing projects by Argonne National Laboratories and subcontractors related to high-temperature batteries.

Section I introduces the material contained in the rest of the report. Section II presents the origin and characteristics of humic materials as we understand them today and outlines the methods that have been used to separate and analyze these substances. Section III focuses on the general problem of metal-organic interactions and treats some of the factors that are important in chelating and complexing of metal ions by humic substances. Section IV deals specifically with the complexing of radionuclides by organic substances, treated from the standpoint of both empirical and experimental studies.

Aging of simulated nuclear waste glass by contact with a controlled-temperature, humid atmosphere results in the formation of a double hydration layer penetrating the glass, as well as the formation of minerals on the glass surface. The hydration process can be described by Arrhenius behavior between 120 and 240 C. Results suggest that simulated aging reactions are necessary for demonstrating that nuclear waste forms can meet projected Nuclear Regulatory Commission regulations.

MINPACK-1 is a package of Fortran subprograms for the numerical solution of systems of nonlinear equations and nonlinear least-squares problems. This report describes how to implement the package from the tape on which it is transmitted.

In this report we give a detailed presentation of how monitors can be implemented on the HEP using a simple macro processor. We then develop the thesis that a small body of general-purpose monitors can be defined to handle most standard synchronization patterns. We include the macro packages required to implement some of the more common synchronization patterns, including the fairly complex logic discussed in a previous paper. Code produced using these macro packages is portable from one multiprocessing environment to another. Indeed, by recoding the set of basic macros (about 100 lines of code for the Denelcor HEP), most programs that we are new writing could be moved to any similar multiprocessing system.

Report describing the formulation of a finite-element procedure for the implicit transient and static analysis of plate/shell-type structure sin three-dimensional space. It includes a development of the analysis, sample results, a summary, and related appendices.

This paper describes a computational method for improving the accuracy of a given eigenvalue and its associated eigenvector. The method is analogous to iterative improvement for the solution of linear systems. An iterative algorithm using working precision arithmetic is applied to increase the accuracy of the eigenpair. The only extended precision computation is the residual calculation. The method is related to inverse iteration and to Newton's method applied to the eigenvalue problem.

Improving Pollution Prevention and Waste Minimization Program (PP/WMIN) technologies, actions, and culture could be an important cost-cutting step for the US Department of Energy (DOE). Communicating ideas, concepts, process changes, and achievements is essential for the success of this program. The need to openly communicate ideas and concepts in a cost-effective manner is essential in an organization that has such diverse components as research and development, weapons production, and power generation. This approach is in contrast to the historic DOE culture developed within the cold war period in which compartmentalization, independence, and secrecy were stressed. DOE has now recognized that for any pollution prevention program to be successful, the many diverse elements of the organization must share information. Avenues for such information exchange are examined in this report.