The organizing philosophy and components of a target diagnostics data acquisition system designed and implemented at the Lawrence Livermore Laboratory (LLL) Shiva Laser Fusion Facility are described. Several features of the system are unique: a central trigger distribution system, fiber optic communications, and fiber optics for the timing, trigger, and control and monitoring links. The system also uses CAMAC instrumentation, transient digitizers, oscilloscopes, and LLL-designed modules and packages, as well as single-point grounding of each diagnostic installation. Distributed instrumentation packages provide instrumentation flexibility and analog-to-digital conversion as close to each diagnostic sensor as practical.

The success of any Inertial Confinement Fusion system for the production of useful power depends critically on the production of suitable targets. This is true whether the arrangement is that proposed by Nuckolls et al. or some other arrangement. The target must have characteristics such as material composition, structure, and surface finish which are tailored to the laser pulse length, energy, peak and average power and pulse shape. To provide useful power on a continuous basis, it is likely that the repetition rate will be 1.0 to 10 per second. Thus, in a 24 hour running period 864,000 targets may be necessary and one must be placed at the focal point of the laser every tenth of a second. For economic operation it is necessary that the targets be produced at costs of less than $1.00 per target.

An inducer pump has been designed to fit within the existing housing of the FFTF Facility. The design has been shown to meet the specified requirements in every area where an analytical prediction of the performance can be made. The head-rise and efficiency of the pump have design margins so that the calculated values actually exceed requirements over the full range of operation. The suction performance of the design provides a very large margin at the operating NPSH value which is the major advantage of using the inducer pump. The suction performance margin at off-design is estimated to be adequate for suction performance, but may not be as large as desired for life considerations. The design has incorporated features that provide for long life at the design point. These features have been established based on proven performance of commercial waterjet pumps designed by Rocketdyne.

The nuclear design analysis and performance of the blanket for the Pu/sup 239/ producing standard mirror hybrid is discussed. The blanket is based on present day materials and technology. It is designed for peak power density and burnup in the uranium fuel of 500 W/cc and 3 atom percent. The blanket produces 2.0 Mg/yr of Pu-239 (net) from 400 MW fusion (D-T) and depleted uranium and has an average energy multiplication of 11.

Measurements of the dilution of air contaminants between worker breathing zone and area air samplers were made by releasing a test aerosol in a workroom equipped with an aerosol surveillance system. The data were used to evaluate performance, and suggest improvements in design of the workroom's alarming air monitor system. It was found that a breathing zone concentration of 960 times the maximum permissible concentration in air (MPC/sub a/) for a half-hour was required to trigger alarms of the existing monitoring system under some release conditions. Alternative air monitor placement, suggested from dilution measurements, would reduce this average triggering concentration to 354 MPC/sub a/. Deployment of additional air monitors could further reduce the average triggering concentration to 241 MPC/sub a/. The relation between number of monitors and triggering concentration was studied. No significant decrease in average triggering concentration was noted for arrays containing greater than five monitors.

A description of the light-water reactor (LWR) fuel cycle and the nature of the radioactive wastes is basic to the design and evaluation of terminal waste repositories. For these projections, the fuel cycle is represented as a typical system of operations related to the back end of the LWR fuel cycle. Wastes, as prepared for disposal, are described in terms of form, volume, radioactivity, heat generation, and weight. To obtain these waste projections, three fuel management computer codes were used: ORIGEN, KWIKPLAN, and WASPR. A brief description of these codes and their usage is included. Also included are descriptions of the containers assumed to be used for the handling and geologic disposal of the various waste types. The data generated for the Office of Waste Isolation (OWI) and its subcontractors are documented. Projections of LWR fuel cycle wastes are based on OWI modification of the ERDA mid-case forecast of 1976 for nuclear power growth in the United States. In this case, the installed nuclear electric capacity rises from a nominal 50 GW(e) in year 1977 to a nominal 480 GW(e) in the year 2000. The power reactor grid is assumed to consist entirely of LWRs. The four basic fuel cycle …

The DT fusion neutron irradiation of two LLL superconductor wires at 4.2/sup 0/K is described. The sample position, beam-on time, and neutron dose record are given. The results from four ''profile'' dosimetry foils measuring the lateral variation in neutron flux are included.

A reactor based on this concept that produces 1000 MWe consists of a solenoidal magnet about 50 to 100 m long. A cylindrical blanket is used for energy recovery and tritium breeding. Thus the reactor itself is simple and of low technology. The end plugs, however, are of high technology, having the high magnetic fields needed to confine the high-pressure plasma and the high injection energy (0.6 to 1.2 MeV) needed to achieve good magnetic confinement. A low technology, compact, economical hybrid fusion-fission reactor results from injection in the central cell as well as the ends, provided a means can be found to stabilize the end plugs against microinstabilities, particularly in small sizes (plug radius divided by ion gyroradius less than or equal to 10). The Q value is 1.8 and the power is 500 MWe, with 1000 kG of /sup 233/U produced per year. If, on the other hand, the tandem is operated in the two-component mode (i.e., cold tritium plasma electrostatically contained into which a 100-200 keV D/sup 0/ beam is injected), then the end plugs can be stabilized by the outward flowing tritium plasma. Finally, we show that D-D burning tandem reactors appear feasible in large sizes …

Be/sup 10/ has long been of interest for cosmic ray propagation, because its radioactive decay half-life is well matched to the expected cosmic ray age. Recent beryllium isotope measurements from satellites and balloons have covered an energy range from about 30 to 300 MeV/nucleon/sup 1-3/. At the lowest energies, most of the Be/sup 10/ is absent, indicating a cosmic ray lifetime of order 2 x 10/sup 7/ years and the rather low average density of 0.2 atoms/cc traversed by the cosmic rays. At higher energies, a greater proportion of Be/sup 10/ is observed, indicating a somewhat shorter lifetime. These experiments will be reviewed and then compared with a new experiment covering from 100 to 1000 Mev/nucleon/sup 4/. Although improved experiments will be necessary to realize the full potential of cosmic ray beryllium isotope measurements, these first results are already disclosing interesting and unexpected facts about cosmic ray acceleration and propagation.

A theoretical study was made of the radiative heat removal capability in a 19-pin bundle simulating the fuel assemblies of the commercial-scale (217-pin) Clinch River Breeder Reactor. Pin surface temperature distributions and the maximum allowable uniform pin power (without causing cladding meltdown) were determined for a range of emissivities and duct-wall temperatures. It was concluded that radiative heat transfer ranging to 0.1 kW/ft was comparable to free convection ranging to 0.02 kW/ft, and was lower than that of forced convection cooling to 2.17 kW/ft by the sodium vapor.

The DT fusion neutron irradiation of two ORNL magnesium oxide crystals and eleven BNL-LASL superconductor wires is described. The sample position and neutron dose record are given. The maximum neutron fluence on any sample was 2.16 x 10/sup 16/ neutrons/cm/sup 2/.

Manganin stress gages have been fabricated and used successfully to study initiation and detonation of high explosives. These four-terminal, low-impedance gages have been specially designed and encapsulated to minimize the effects of various gage failure mechanisms. Several candidate dielectric encapsulation materials have been tested in the reactive environment, and of these polytetrafluoroethylene has been chosen. Gage stations are formed by thermally bonding the manganin foil between layers of this dielectric. Gages manufactured in this way have been used to provide stress profiles throughout the region of build-up to detonation in PBX-9404 and TATB.

The effects of superficial liquid and gas velocity, particle diameter, liquid viscosity, and column diameter on liquid dispersion (E/sub L) and mass transfer (K/sub L/a) in three-phase fluidized beds were investigated using a water--glycerol/oxygen--nitrogen (or oxygen--argon)/glass-bead system. Overall mass transfer coefficients were calculated based on plug flow, dispersed plug flow, and continuously stirred tank models. k/sub L/a was found to increase with gas velocity and particle diameter, but no correlation of K/sub L/a with liquid velocity was observed. At low liquid velocities, K/sub L/a was lower for the more viscous liquid; the reverse was true at high liquid flow rates. E/sub L/ increased rapidly for liquid flow rates at two to three times the minimum fluidization velocity.

A brief but comprehensive summary of a conceptual design for an OTEC platform is presented. In the first phase studies, an evaluation methodology was developed for analyzing the ocean system requirements against site criteria and a final evaluation of integrated OTEC commercial platform candidates was performed. A ranking of candidate platforms was obtained as the end result. For Phase-II studies, M. Rosenblatt and Son, Inc. project team was given the SPAR and SPHERE platforms to perform not only the conceptual designs for, but also cost and time schedules and sensitivity analyses. The commercial plant size was specified to be 400 MWe (net). All conceptual design work was performed for the baseline site on West Coast of Florida. The cost differentials and other considerations involved with deploying the platforms in the New Orleans and Puerto Rico sites were also determined. A demonstration plant of 100 MWe (net) capacity, to fill the gap between test platforms and commercial plants, was also investigated, and a project plan was developed. As an end product of the complete study, the costs for the SPAR and the SPHERE platforms are reported both in terms of acquisition costs in 1978 dollars and life cycle costs in dollars …

The activities associated with the procurement of the materials for the screening test program, information from vendor certification for the materials received, and preliminary information from the materials characterization tests performed by GE are reported. The construction status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment are discussed. The final recommended impurity levels for the screening phase helium are presented and the rational behind this gas chemistry is discussed. The status of the data management system is presented.

Rubidium fluoride and niobium metal-containing foam samples (rods and sheets) were prepared using two foam sytems: (1) hydrophilic polyurethanes prepared from W.R. Grace Co.'s Hypol prepolymers and (2) polyimides prepared from Monsanto Company's Skybond polyimide resin. The first system was used only for preparation of rubidium fluoride-containing foams while the second was used for both rubidium fluoride and niobium-containing foams. The niobium metal could readily be incorporated into the polyimide foam during molding, to produce foam sheets of the required dimensions and density. The rubidium fluoride-containing polyimide foams were preferably prepared by first rendering the molded polyimide foam hydrophilic with a postcuring treatment, then absorbing the rubidium fluoride from water solution. Similarly, rubidium fluoride was absorbed into the hydrophilic polyurethanes from water solution. Since the high reactive rubidium metal could not be employed, rubidium fluoride, which is very hygroscopic, was used instead, primarily because of its high rubidium content (approximately 82 weight percent). This was important in view of the low total densities and the high weight percentage rubidium required in the foam samples. In addition, at the later request of LLL, a block of rigid Hypol hydrophilic polyurethane foam (with a density of approximately 0.04 g/cm/sup 3/ and cell …

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 167R, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 167R was conducted to obtain thermal-hydraulic and CHF information in THTF bundle 1 with an intact cold leg. The primary purpose of this report is to make the reduced instrument responses during test 167R available. These are presented in graphical form in engineering units and have been analyzed only to the extent necessary to ensure reasonableness and consistency.

A process sequence is proposed and analyzed with regard to yield and cost of direct materials for fabrication. Cells of at least 13% conversion efficiency and panels of 10% efficiency have been assumed. Material costs, excluding silicon, were estimated as low as $0.19/watt (1975). Use of the JPL Interim Price Estimation Guidelines gives a projected contribution to selling price of $0.24/watt (1975) for the direct materials used in processing. If silicon is included, the contribution to selling price is $0.46/watt (1975). Development effort during this quarter has been applied to junction information, anti-reflection coating and laser scribing. Junction formation effort was in two areas: (1) establishing the process parameter ranges for the back surface diffusion from a boron-doped oxide and for the front junction diffusion using POCl/sub 3/ and (2) determining if the purity of the POCl/sub 3/ source material is critical to cell performance. Anti-reflection coatings of TiO/sub 2/ have been prepared on cells formed in dendritic web silicon by spin-on application of a liquid metallo-organic precursor.Achievement of 12 to 13% conversion efficiency after single layer coating was common. Laser scribing to remove dendrites from the ribbon and to delineate cell areas has been demonstrated. The presence of photoresist, …

Quantitative estimates of charge exchange (CE) losses during acceleration are very important in the design and operation of heavy ion cyclotrons. Such estimates have been made using a vacuum model computer code which was developed to establish vacuum requirements for the MSU superconducting heavy ion cyclotron. This code uses pressure and cross-section data to calculate the radial loss of beam due to charge exchange. Since CE cross sections and radial pressure profiles are not always well known, certain specific measurements have been made using the LBL 88-Inch Cyclotron to provide experimental data needed to test the code. These include measurements of pressure versus radius under vacuum conditions closely approximating those existing during acceleration of /sup 14/N/sup 4 -/ and /sup 40/Ar/sup 8 -/ beams. Beam intensity versus radius data demonstrating transmission losses for three beams are presented. Comparisons with theoretical predictions are given.

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; Whether a completed compromise settlement agreement constitutes a claim for compensation within article 8307 section 9a(e)(2),V.T.C.S

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 article 21.48A, Insurance Code, prohibits a lender from refusing to accept property insurance policies from a company.

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 a county under the Airport Zoning Act.

Data collected as part of hydrogeochemical and stream sediment reconnaissance data for Oklahoma City NTMS quadrangle including laboratory data on well water, spring water, and stream sediments as well as field data.