A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.

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; May a person elected city commissioner remain pecuniarily interested in a contract previously entered into with the city whereby the city sells water to him for resale to rural customers.

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 state and local sales tax must be collected on items sold to inmates of the Harris County Jail and Harris County Rehabilitation Center from commissioners located at each facility.

Report that presents information regarding chemical and radioactive pollution in the world. Includes tabulations of radionuclides and lead in milk, food, and tapwater.

Report documenting radioactive fallout across the world, including both material in the atmosphere and that has deposited into food supplies.

Report documenting radioactive fallout across the world, including both material in the atmosphere and that has deposited into food supplies. This appendix includes tables of monthly fallout deposition collections from 116 sites across the Earth and a list of radionuclides and their half-lives.

The objective of this paper is to summarize measured resuspension concentrations and to consider the implications of these results. In these experiments, airborne concentrations were measured as functions of wind speed, airborne particle size, wind direction, and the collected-plutonium and other nuclides per gram of airborne soil. Airborne radionuclides were normalized by the total amount of airborne solids to relate concentration per gram of airborne solid to concentration per gram of radionuclide on the ground.

This brochure is designed as a basic source of information for prospective users of Sandia Laboratories Radiation Facilities. It contains a brief description of the various major radiation sources, a summary of their output characteristics, and additional information useful to experimenters. Radiation source development and source upgrading is an ongoing program, with new source configurations and modes of operation continually being devised to satisfy the ever-changing radiation requirements of the users. For most cases, the information presented here should allow a potential user to assess the applicability of a particular radiation facility to a proposed experiment and to permit some preirradiation calculations and planning.

This bibliography of 500 references is compiled from the Data Base on the Environmental Aspects of the Transuranics built to provide information support to the Nevada Applied Ecology Group (NAEG) of ERDA`s Nevada Operations Office. The general scope is environmental aspects of uranium and the transuranic elements, with emphasis on plutonium. Laboratory and field studies dealing with the effects of plutonium-239 on animals are highlighted in this bibliography. Supporting information on ecology of the Nevada Test Site and reviews on the effects of other radionuclides upon man and his environment has been included at the request of the NAEG. The references are arranged by subject category with first authors appearing alphabetically in each category. Indexes are given for author, geographic location, keywords, taxons, permuted title and publication description.

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A total of six pilot-scale batches of picryl chloride were made. These included three 5-kg batches and three 10-kg batches. The three 5-kg batches were made to investigate the problems encountered with actual production and materials handling. The three 10-kg batches were made to study the process parameters and the yield problems originally encountered with the 5-kg batches. The yields on the 5-kg batches ranged from 40 to 60% of approximately 50% purity. The yields on the 10-kg batches were 80, 86 and 91% in chronological order. The purities were 95, 99+ and 99+% respectively.

During the time period of February to April, 1979, twelve rod extensometers and twenty-two convergence measurement points were installed, calibrated and monitored in support of the spent fuel mine in granite. Readings taken during heading and bench advance shows good instrument stability, with little or no anchor creep or slippage. Repeat calibrations indicate excellent repeatability. Measurement points within the heater drifts indicate little closure. Convergence pins within the spent fuel drift were subjected to significant blast damage that resulted in a discontinuous record. A numerical analysis of the stresses and displacements of the rock mass as a result of the mine-by was performed. Two methods, finite element and displacement discontinuity, were used to model the mine-by. Comparison of the actual to predicted displacements show good agreement for the 33{sup 0} and 50{sup 0} extensometers for a rock mass modulus of 3 to 5 x 10{sup 6} psi and Poisson`s ratio of .2. The horizontal extensometers however indicate a convergence of anchor and collar (divergence predicted) and the IRAD stressmeters installed within the pillar indicate a significant reduction in vertical compression during mining of the heading. A simple reduction of pillar modulus will not account for the observed stress and displacement …

This brochure is designed as a basic source of information for prospective users of Sandia Laboratories Radiation Facilities. It contains a brief description of the various major radiation sources, a summary of their output characteristics, and additional information useful to experimenters. Radiation source development and source upgrading is an ongoing program, with new source configurations and modes of operation continually being devised to satisfy the ever-changing radiation requirements of the users. For most cases, the information here should allow a potential user to assess the applicability of a particular radiation facility to a proposed experiment and to permit some preirradiation calculations and planning.

The experimental results obtained from investigation of the radionuclide distribution in the environment around the detonation point of the 0.75-kt nuclear test, Cambric, fired 300 m underground in alluvium at the Nevada Test Site in 1965, are presented and discussed. Analyses of sidewall cores obtained ten years later from near ground surface to below the explosion cavity showed that most of the radioactivity is still contained within solid material in the lower cavity region. Water pumped from the region of highest activity at the bottom of the cavity showed only T and {sup 90}Sr at levels higher than the recommended concentration guides for drinking water in uncontrolled areas. Recommendations for future studies are given. The investigation is part of the Radionuclide Migration Project sponsored by the Nevada Operations Office of ERDA.

For the vapor phase of the WVN process the 160 to 190{sup 0}F temperature limit is shown to be well within the 145 to 208{sup 0}F minimum/maximum range. Decreasing process time by expansion of the temperature range is not expected to aid processing. The most productive area for improvement would be an increase in the water vapor concentration above the present 5% level. However, this would require confirmatory testing before approved use. The rinsing process was shown to be mainly controlled by component crevice geometry. Improvements in rinse time may be made by increasing the water temperature, but the concern over the caustic stress corrosion cracking will tend to limit the available increase. Although directed jets or sprays of rinse flows was not recommended, methods were suggested for conserving rinse water. Drying (as well as heating and cooling) of components was again shown to be constrained mostly by individual geometry and not processing parameters. A gas only, vacuum only, or a combination of the two modes were shown to be generally accepted methods. The hot gas only mode was recommended for its simplicity.

The intensity and spectral characteristics of x-ray emitted from laser-produced plasmas have been investigated computatinoally and experimentally. a two-dimensional implosi code was used successfully to calculate laser-plasma radiation characteristics and to aid in the design of laser targets for high-yield x-ray production. Other computer codes, in use or under development predict lime strengths and energies for laser-plasma x-ray emission. An experimental effort is aimed at reliable measurements of x-ray yields and spectra. a wide variety of x-ray detection methods have been evaluated, and x-ray yields have been measured from plasmas produced with two dissimilar laser systems. The high energy x-ray spectrum, from about 10 to 140 keV, has been studied using high-gain scintillatino detectors and thick K-edge filters. Various supplementary measurements have provided information concerning characteristics of the target-reflected laser light, the ion energies, and the laser intensity patterns.

This report surveys the need for large computers in analyzing the properties of magnetically confined plasmas and simulating the characteristics of fusion reactors. The major conclusion of the report is that, to meet the program schedule developed by Magnetic Confinement Systems, it would be necessary to immediately scale up the CTR (controlled thermonuclear research) computerized effort to a level of two Class IV computers by FY 1975. Based on this report, and in an attempt to best meet this need, it was decided to establish the National CTR Computer Center at the Lawrence Livermore Laboratory.

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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 …

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 report describes the methodology for determining where environmental control technology is required for the nuclear fuel cycle. The methodology addresses routine emission of chemical and radioactive effluents, and applies to mining, milling, conversion, enrichment, fuel fabrication, reactors (LWR and BWR) and fuel reprocessing. Chemical and radioactive effluents are evaluated independently. Radioactive effluents are evaluated on the basis of maximum exposed individual dose and population dose calculations for a 1-year emission period and a 50-year commitment. Sources of radionuclides for each facility are then listed according to their relative contribution to the total calculated dose. Effluent, ambient and toxicology standards are used to evaluate the effect of chemical effluents. First, each chemical and source configuration is determined. Sources are tagged if they exceed existirrg standards. The combined effect of all chemicals is assessed for each facility. If the additive effects are unacceptable, then additional control technology is recommended. Finally, sources and their chemicals at each facility are ranked according to their relative contribution to the ambient pollution level. This ranking identifies those sources most in need of environmental control.

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 experiment requirements and objectives for the reactivity initiated accident (RIA) tests to be conducted in the Power Burst Facility (PBF) are described 1n the RIA Experiment Requirements Document (ERD) The primary objectives of the RIA research 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 BWRs will be used in the Series 1 tests. The first R!A test outlined in the ERD, RIA 1-1, is to be performed using four test fuel rods (two unirradiated and two irradiated) in the four rod hardware. The test fuel rods are to be exposed to a power transient in PBF which deposits an anergy of about 300 cal/g at 90% of the fuel radius (i.e. near the fuel surface). This will be the first RIA experiment ever perfonned at hot startup conditions and three potential problems have been identified since the ERD was written. These problem areas are: identification of the fuel failure threshold energy deposition for hot-startup conditions, evaluation of calorimetry techniques for RIA transient tests, and determination of possible pressure pulses that can result …

Sixteen heat source assemblies have been tested in support of the SNAP 19 Pioneer Safety Test Program. Seven were subjected to simulated reentry heating in various plasma arc facilities followed by impact on earth or granite. Six assemblies were tested under abort accident conditions of overpressure, shrapnel impact, and solid and liquid propellant fires. Three capsules were hot impacted under Transit capsule impact conditions to verify comparability of test results between the two similar capsule designs, thus utilizing both Pioneer and Transit Safety Test results to support the Safety Analysis Report for Pioneer. The tests have shown the fuel is contained under all nominal accident environments with the exception of minor capsule cracks under severe impact and solid fire environments. No catastrophic capsule failures occurred in this test which would release large quantities of fuel. In no test was fuel visible to the eye following impact or fire. Breached capsules were defined as those which exhibit thoria contamination on its surface following a test, or one which exhibited visible cracks in the post test metallographic analyses.