A fused fluoride process for dissolution of zirconium-uranium fuel alloys is being developed. The alloy is dissolved in an equimolar sodium fluoride-zirconium fluoride melt at 600°C by sparging the system with hydrogen fluoride. The uranium is volatilized from the melt as the hexafluoride by a sparging operation with fluorine or bromine pentafluoride vapor. This product is then decontaminated and purified by fractional distillation.

Physical calculations have been performed for various combinations of the four types of fuel assemblies to be used in the EBWR core. Two thicknesses of plates (0.205 in. and 0.274 in., including two 0.020-in. cladding layers) are to be made of both natural uranium and uranium containing 1.44% U235. Any given fuel assembly contains six identical plates. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated. Various configurations of these fuel assemblies can be used to (1) change the critical size of the core, (2) change the power distribution in the core or (3) change the amount of reactivity corresponding to a given steam volume in the core. Physics calculations show that any uncertainties in the required critical mass are adequately covered by the number and variety of fuel assemblies, and that the changes in core characteristics possible with the different fuel assemblies should provide valuable information about the factors affecting maximum power density and stability in a boiling reactor.

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).

Concurrently with the production of canned uranium slugs for pile operation there arises the problem of nondestructive testing so that no slug which may fail structurally during operation be placed in the pile. The ultimate goal of any such testing program is to devise nondestructive testing methods which will eliminate defective slugs. A secondary goal of the testing program is to learn as much as possible about the construction of the canned slug so that the mechanisms of failure can be understood. Radiography, an increasingly useful nondestructive test method, offered one possible way of investigating this area.

A plutonium-aluminum alloy containing 4 atom per cent aluminum showed no attack after exposure to purified NaK for one month at 400 C in the absence of any oxide. The same specimen and other plutonium alloys, including pure plutonium, showed marked deterioration in shorter exposure in the presence of oxide films from a welded stainless steel container. Pure uranium was resistant even in the presence of such oxides.

The purpose of this work was to study reagents which might be effective in dissolving uranium oxide produced during slug failures in water-cooled reactor systems. An aspect of this problem which has subsequently become of primary importance is the solubility or transportability of the oxide in pure water.

A method for monitoring radiation damage irradiations using the change of the electrical conductivity of graphite is described. Results of monitoring operations in a number of locations are given. An attempt is made to explain the damage rate found in the converter at CP-3. An estimate of the flux spectrum in VT-4 and the converter of CP-3 is made and the damage rate is computed according to theories of Seitz and James. It is found that the experimental results are more in accord with the predictions of Seitz. A number of corrections to James' report, ORNL-307, are noted in an appendix. It is shown that some information about the fast flux spectrum can be inferred from the radiation damage rate.

Annual report of the Ion Replacement Electrorefining Program at Aronne National Laboratory describing their research and activities. There are three key accomplishments highlighted for the year: (1) identification of a suitable sodium(beta){double_prime}-alumina/molten salt electrolyte system that functions reproducibly at 723 K, (2) actual separation of dysprosium and lanthanum in experiments, and (3) the identification of a metal alloy, Li{sub x}Sb, as an alternative ion replacement electrode.

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.

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.

This report contains historical information on the Li-alloy/FeS system that will be useful in its future applications. This document includes the following: (1) the chemical and electrochemical reactions for the Li-alloy/FeS system, accomplishments in past cell development efforts, and performance attained by state-of-the-art cells vs performance goals; (2) detailed drawings of state-of-the-art cell designs, documentation of cell fabrication techniques, and comparisons of alternative types of cell components (such as BN felt vs MgO powder separators, stainless vs low-carbon steel cell housings) and fabrication techniques (such as charged vs uncharged electrodes); (3) results of post-test cell analyses, including cell failure mechanisms, electrode morphology and active material distribution, and in-cell corrosion rates; (4) data from trade-off studies between specific power and energy; (5) discussion of battery design considerations (e.g., volumetric energy density, battery charger, and high-efficiency thermal insulation); (6) results of cost studies, which include materials and manufacturing costs of cells and batteries and heating costs involved in battery operation; and (7) projections of cell designs having the greatest potential for meeting electric-vehicle performance requirements.

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 report on activities of Argonne National Laboratory's Nuclear Technical Programs, including a review of studies of the ability of backfill to inhibit groundwater flow in a nuclear waste repository.

The Radioactive Liquid Waste Treatment Facility (RLWTF) at Argonne National Laboratory-West (ANL-W) in Idaho provides improved treatment for low-level aqueous waste compared to conventional systems. A unique, patented evaporated system is used in the RLWTF. SHADE (shielded hot air drum evaporator, US Patent No. 4,305,780) is a low-cost disposable unit constructed from standard components and is self-shielded. The results of testing and recent operations indicate that evaporation rates of 2 to 6 gph (8 to 23 L/h) can be achieved with a single unit housed in a standard 30-gal (114-L) drum container. The operating experience has confirmed the design evaporation rate of 60,000 gal (227,000 L) per year, using six SHADE's.

Performance of improved Ni/Fe electric vehicle batteries was measured at ambient temperatures of 0, 25, and 50 C for a range of overcharge levels, open-circuit stand times, and charge and discharge rates. Tests in which charges and discharges were performed at different battery operating temperatures showed that the discharge capacity of a Ni/Fe battery is directly related to its operating temperature, but its charge acceptance is decreased at 0 and 50 C by approx. 6% from that obtained at 25 C. The decline in battery efficiency at high temperatures is the result of increased self-discharge losses. In the first 0.5 h after charge, the Ah self-discharge loss at 50 C is twice (6%) that at 0 and 25 C (approx. 3%), corresponding to an increase in initial self-discharge rate from approx. 8 to 16 A. The increased self-discharge rate apparently occurs during the latter part of charging and, thereby, causes the 6% decline in charge acceptance. A decrease in battery efficiency also resulted at 50 C (6% coulombic and 4% energy efficiency loss) when the charge current was reduced from the 3-h to the 6-h rate. In comparison, low temperatures impact battery internal resistance and IR-free voltage more than high …

A set of macro libraries has been developed that allows programmers to write portable FORTRAN code for multiprocessors. This document presents, in tutorial form, the macros used to implement three common synchronization patterns: self-scheduling DO-loops, barrier synchronization, and the askfor monitor.

A set of macro libraries has been developed that allows programmers to write portable Pascal code for multiprocessors. This document presents, in tutorial form, the macros used to implement three common synchronization patterns: self-scheduling FOR-loops, barrier synchronization, and the askfor monitor.

Computer model simulation is required to evaluate the performance of proposed or future high-level radioactive waste geological repositories. However, the accuracy of a model in predicting the real situation depends on how well the values of the transport properties are prescribed as input parameters. Knowledge of transport parameters is therefore essential. We have modeled ANL's Experiment Analog Program which was designed to simulate long-term radwaste migration process by groundwater flowing through a high-level radioactive waste repository. Using this model and experimental measurements, we have evaluated neptunium (actinide) deposition velocity and analyzed the complex phenomena of simultaneous deposition, erosion, and re-entrainment of bentonite when groundwater is flowing through a narrow crack in a basalt rock. The present modeling demonstrates that we can obtain the values of transport parameters, as added information without any additional cost, from the available measurements of laboratory analog experiments.

This report summarizes the work that has been performed to date at Argonne National Laboratory on the development of the TRUEX process, a solvent extraction process employing a bifunctional organophosphorous reagent in a PUREX process solverc (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste.

In this report it is shown that a burner placed in a combustible fluid can have a stabilizing effect on a plane flame. A mathematical model is derived in which the flame is modeled as a surface of discontinuity in the flow field. Jump conditions for the fluid variables, as well as an expression for the flame speed, are obtained from an asymptotic analysis of the detailed structure of the flame. The model is applied to investigate the linear stability of a plane flame. Stable behavior is shown to exist for certain regimes of the parameters: Lewis number, burner strength, heat release and inflow velocity.

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to ecology. This report discuses programs including a development project for microcosm screening systems, two initiatives in ecological modeling, and a program of field experiments for a national assessment of crop losses due to air pollution.

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to ecology and funding issues during the year.

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.