Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, John L. Hill, regarding a legal question submitted for clarification: Authority of LCRA to permit another entity to use part of pipeline and consequences of transaction.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, John L. Hill, regarding a legal question submitted for clarification: Distribution and use of probation fees.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, John L. Hill, regarding a legal question submitted for clarification: Whether Harris County may restrict the award of printing jobs to union printers.

Monthly newsletter of the Alamo Area Council of Governments describing news and events of relevance to the agencies.

The creep-fatigue life results for five different heats of Type 304 stainless steel at 593 degrees C (1100 degrees F), generated under push-pull conditions in the axial strain-control mode, are presented. The life predictions for the various heats based on the linear-damage rule, strain-range partitioning method, and damage-rate approach are discussed. The appropriate material properties required for computation of fatigue life are also included.

The bilinear cyclic stress-strain parameters for Types 304 and 316 stainless steel are described. The bilinear properties of solution-annealed and aged Type 304 stainless steel (heat 9T2796) and solution-annealed Type 3l6 stainless steel (heat 8092297) under cyclic-loading conditions at a strain rate of 8.6 x 10⁵ s⁻¹, total strain range between 0.2 and 0.8 percent, and temperatures from 22 to 593 degrees C were determined. The dependence of bilinear parameters on maximum strain epsilon and temperature is discussed.

An analysis has been made of the combined motion of fuel and coolant due to fuel-coolant interactions following a massive fuel failure in a high-ramp overpower transient. The motion of fuel and coolant was described using a two-fluid model formulation in which the mixture of sodium liquid and vapor and of fission gas, on the one hand, and the fuel particles, on the other, were treated as two superimposed continua. The method of solution employed a numerical procedure called the ACE method, a modified version of the IMF technique.

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.

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

Report describing the research and development activities related to reactor fuels and fast-reactor programs conducted by the Argonne National Laboratory Chemical Engineering Division.

The interim draft report containing the first stage of CSC`s work on prediction of subsurface ground motion was completed. Twenty-four stations of the seismic monitoring network are now operational. The location for the first exploratory hole in Calico Hills was changed based on interpretation of magnetic and electrical geophysical data. Two core holes were completed in the Climax Stock in the Pile Driver tunnel complex. Drilling on the first exploratory hole at Yucca Mountain commenced on July 30, 1978. Field reconnaissance of granitic rocks in southern Nevada continued, including locations in Esmeralda, Nye, and White Pine Counties. The modeling of the Eleana Heater Experiment showed good agreement with field temperature data for conduction energy transfer. A rough draft of the tuff scoping report was completed. Review of the LASL quality program plan for their activities on the NTS Terminal Waste Storage Program was completed by Sandia Quality Assurance. A geological reconnaissance of the region near the Yucca Mountain drill site suggested a high probability that large, reasonably unfaulted blocks of tuff exist in the area.

The Plutonium(IV) Oxalate Precipitation and Calcination Process for converting plutonium nitrate to plutonium oxide is described for a 100-kg plutonium per day (Pu/day/ throughput facility. Block flow diagrams, equipment flowsheets, and stream material balances are included. Advantages and disadvantages of the process, additional research and development necessary, and history of the process are also discussed. This report is one of a series describing various processes for converting plutonium nitrate to oxide. This information in this report should be used when comparing the various processes, and as a starting point for development of a prototype or plant-scale facility.

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The work reported herein is a continuation of the program initiated under DOE contract E(10-1)-1546* entitled "Program to Design and Experimentally Test an Improved Geothermal Bit"; the program is now DOE Contract EG-76-C-1546*. The objective of the program has been to accelerate the commercial availability of a tolling cutter drill bit for geothermal applications. Data and experimental tests needed to develop a bit suited to the harsh thermal, abrasive, and chemical environment of the more problematic geothermal wells, including those drilled with air, have been obtained. Efforts were directed at the improvement of both the sealed (lubricated) and unsealed types of bits. The unsealed bit effort included determination of the rationale for materials selection, the selection of steels for the bit body, cutters, and bearings, the selection of tungsten carbide alloys for the friction bearing, and preliminary investigation of optimized tungsten carbide drilling inserts. Bits build** with the new materials were tested under stimulated wellbore conditions. The sealed bit effort provided for the evaluation of candidate high temperature seals and lubricants, utilizing two specially developed test apparatus which simulate the conditions found in a sealed bit operating in a geothermal wellbore. Phase I of the program was devoted largely to …

Electropolishing is a rapid and effective technique for removing plutonium and other radionuclide contamination from a variety of metal surfaces. The major objective of this continuing research is to develop electropolishing into a large-scale decontamination technique that can completely and economically remove transuranic and other surface contamination from large volumes of metallic waste. These research studies have demonstrated the ability of electropolishing to reduce the radiation levels of steel tools and stainless steel vacuum system components, which were heavily contaminated with plutonium oxide. Other examples of objects that have been decontaminated within minutes using electropolishing include hot cell manipulator assemblies, analytical instrument components, laboratory transfer containers, offsite shipping containers, fission product storage capsules, laboratory animal cages, and nuclear reactor process tube components. One of the major activities of this research has been the establishment and intensive operation of a 400-gal immersion electropolishing system designed specifically to develop and demonstrate decontamination techniques for representative plutonium- and beta/gamma-contaminated components. Substantial progress has also been made in developing in situ electropolishing techniques that can be used to decontaminate metallic surfaces that cannot readily be transported to or immersed in a conventional electropolishing tank. Sectioning/pretreatment studies are underway to develop and demonstrate optimum disassembly, …

In this phase of work the Process Development Unit (PDU) is to be remodeled by incorporation of appropriate subsystems to permit operation in continuous process mode. The PDU will be operated for a period of time sufficient to demonstrate process viability.

This document describes the experiment operating specifications for the Reactivity Initiated Accident (RIA) Test RIA 1-2 to be conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The RIA Series I research objectives are to determine fuel failure thresholds, modes and consequences as functions of enthalpy insertion, irradiation history, and fuel design. Coolant conditions of pressure, temperature, and flow rate that are typical of hot-startup conditions in commercial boiling water reactors {BWRs) will be used. The second test in Series I, Test RIA 1-2, will be comprised of four individual rods, each surrounded by a separate flow shroud. The four rods will be preirradiated. The specific objectives of the test are to: (1) characterize the response of preirradiated fuel rods during a RIA event conducted at BWR hot-startup conditions and (2) evaluate the effect of internal rod pressure on preirradiated fuel rod transient response. The test sequence will begin with steady state power operation to condition the fuel (pellet cracking and relocation) and determine the fuel rod power calibration. The loop will then be cooled down, the test train removed from the in-pile tube, and the cobalt flux wires that are mounted on each flow shroud …

The objectives of the Fuel Performance Improvement Program (FPIP) are to identify and demonstrate fuel concepts with improved performance and to provide the supportive technical bases for developing commercial fuel designs that are capable of achieving hiqh burnup for better utilization of uranium.

The application of conducting plastic mixtures to the fundamental problem of radiation Dosimetry is briefly reviewed. A particular approach to achieveing formulations with the necessary characteristics is decribed. A number of successful mixtures are defined for a number of different specific dosimetry situations. To obtain high quality stable materials requires intense blending·and working of the materials at elevated temperatures. One machine that succeeds in this task is the Shonka plastics mixer-extruder. The Shonka mixer is described in complete detail. The procedures used in preparing represeptative formulations with this device are presented. A number of properties of successful conducting mixtures so prepared are summarized. The conditions required for molding such material are given. Several special welding methods for specific application with these formulations have been devised and are described.

Plutonium is one of the principal materials of both commercial and military nuclear power. It is produced primarily in fission reactors that contain uranium fuel, and its importance arises from the fact that a large portion of the plutonium produced is fissile: like uranium 235, the mass 239 and 241 isotopes of plutonium can be caused to fission by neutrons, including those with low energy. Because such fission events also release neutrons, substantial amounts of energy can be extracted from plutonium in a controlled or an explosive nuclear chain reaction. Now that commercial nuclear reactors provide a noticeable fraction of United States (and world) electrical energy, these reactors account for most plutonium production. For the most part, this material now remains in the irradiated fuel after removal from reactors, but should this fuel be reprocessed, the plutonium could be recycled to provide part and even most of the fissile content of fresh fuel. For the current generation of water-cooled reactors, the amount of plutonium to be recycled is substantial. In fast breeder reactors, designed to produce more fissile material than they destroy, considerably larger quantities of plutonium would be recycled. In other types of advanced reactors, particularly those which depend …

The use of high rate anodic dissolution (electrochemical machining) for shaping titanium carbide, zirconium carbide, titanium boride and zirconium boride has been investigated in 2N potassium nitrate and 3N sodium chloride under current densities ranging from 20 to 120 A/cm{sup 2} (corresponding to cutting rates of 0.3 to 1.8 mm/min). The dissolution stoichiometry for all these materials is independent of the current density in the range 20 to 120 A/cm{sup 2}. Both titanium and zirconium appear to dissolve in the +4 state, boron in the +3 state and the weight loss measurements indicate that carbon is oxidized to CO and CO{sub 2}. The current voltage curves permit to establish that, over the entire current density and flow range investigated, dissolution occurs in the transpassive state. The surface roughness obtained on TiC and ZrC is within 3-5 {micro}m and is independent of current density, applied voltage or flow rate.

Reaction of optically pure (+) and (-) 7{beta},8{alpha}-dihydroxy-9{alpha},10{alpha}-epoxy-7,8,9.10-tetrahydrobenzo[a]pyrene with DNA in vitro yielded diastereomeric covalent adducts with the exocyclic amino groups of deoxyguanosine and deoxyadenosine. The ratio of two deoxyguanosine diastereomers derived by reacting the (+) and (-) hydrocarbons with native calf thymus and double stranded 0X174 DNA was 20:1 while reaction of the enantiomers with heat denatured calf thymus and single stranded 0X174 DNA resulted in a ratio near 1:1. In contrast, deoxyaadenosine diastereomer pairs were approximately 1:1 in all cases studied. The (+) and (-) enantiomers of the benzo[a]pyrene diol epoxide, therefore, interact asymmetrically with the guanine binding sites of double stranded but not single stranded polydeoxynucleotides. In contrast, reaction of the enantiomers with adenine is not stereoselective.

The July 1978 deflation of the Krafla volcano in the volcanic rift zone of NE-Iceland was in most respects typical of the many deflation events that have occurred at Krafla since December 1975. Separated by periods of slow inflation, the deflation events are characterized by rapid subsidence in the caldera region, volcanic tremor and extensive rifting in the fault swarm that transects the volcano. Earthquakes increase in the caldera region shortly after deflation starts and propagate along the fault swarm away from the central part of the volcano, sometimes as far as 65 km. The deflation events are interpreted as the result of subsurface magmatic movements, when magma from the Krafla reservoir is injected laterally into the fault swarm to form a dyke. In the July 1978 event magma was injected a total distance of 30 km into the northern fault swarm. The dyke tip propagated with the velocity of 0.4-0.5 m/sec during the first 9 hours, but the velocity decreased as the length of the dyke increased. Combined with surface deformation data, these data can be used to estimate the cross sectional area of the dyke and the driving pressure of the magma. The cross sectional area is variable …

On December 8, 1977, Gruy Federal, Inc. took over the C.D. Hopkins et al. No. 2 well, located near Jesup in Wayne County, Georgia, to be deepened and used for geothermal temperature-gradient measurements. The well was drilled from 4,009 to 4,341 feet, then diamond cored to 4,371 feet, 28 feet of core being obtained for analysis. After logging by the USGS District Groundwater Office in Atlanta, the well was terminated with 3 1/2 inch tubing to 4,386 feet. Scientists from Virginia Polytechnic Institute determined the bottom-hole temperature to be 60 C (140 F) at 1,331 meters (4,365 feet). Over the interval 47-1,331 meters (154-4,365 feet) the least-squares temperature gradient was 29.3 {+-} 0.14 C/km (1.61 {+-} 0.25 F/100 ft).