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.

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.

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 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/.

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, …

This study identifies codes, standards, and regulatory requirements for developing design criteria for high-level waste (HLW) canisters for commercial operation. It has been determined that the canister should be designed as a pressure vessel without provision for any overpressure protection type devices. It is recommended that the HLW canister be designed and fabricated to the requirements of the ASME Section III Code, Division 1 rules, for Code Class 3 components. Identification of other applicable industry and regulatory guides and standards are provided in this report. Requirements for the Design Specification are found in the ASME Section III Code. It is recommended that design verification be conducted principally with prototype testing which will encompass normal and accident service conditions during all phases of the canister life. Adequacy of existing quality assurance and licensing standards for the canister was investigated. One of the recommendations derived from this study is a requirement that the canister be N stamped. In addition, acceptance standards for the HLW waste should be established and the waste qualified to those standards before the canister is sealed. A preliminary investigation of use of an overpack for the canister has been made, and it is concluded that the use of …

Ths document is an integral part of the Kilowatt Isotope Power System (KIPS) Program Plan. This document defines the KIPS Reliability Program Plan for the Technology Verification Phase. This document delineates the reliability assurance tasks that are to be accomplished by Sundstrand and its suppliers during the design, fabrication and testing of the KIPS.

A program plan for the project is presented. The report contains summary descriptions of tasks and subtasks and schedules and manpower estimates for the project. The four tasks are: provide technical support to the Transportation Energy Conservation Division; analyze the energy savings implications of shifts in shippers' modal choice from truck to rail freight services; examine on an in-depth basis the total energy demands for two heavy rail passenger systems; and develop detailed analytical methods for comprehensive passenger energy economy studies.

This report supplements Multilith 77-242 (658/62), The Use of Computers by House Members, and Their Staff for Official and Campaign Purposes: Legal and Ethical Issues.

LOFCON is a program developed for the LOFT air condenser system contained in the secondary coolant system. Although the basic theory described herein is general, the program given is not--it is specifically for the LOFT configuration. LOFCON is presented in subroutine form so that it may be easily incorporated into a larger program describing the complete secondary side. Specifically LOFCON was written to be incorporated into the detailed CSMP model of the LOFT secondary coolant system simulation.

From abstract: Results of a reconnaissance geochemical survey of the Oklahoma City Quadrangle, Oklahoma are reported. Field and laboratory data are presented for 812 groundwater samples and 847 stream sediment samples. Statistical and areal distributions of uranium and other possibly uranium-related variables are displayed. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed.

This report

This report is an analysis of the President's Federal Water Policy initiatives of June 6, 1978. Recommendations were made on conservation, cost-sharing, planning procedures, and environmental protection.

This report describes the Section 312 of the Housing Act of 1964, which provides direct, long-term, low-interest rehabilitation loans to individuals whose residential and business properties are located in certain specified program areas.

This report by the National Institute of Education(NIE) is one of six constituting the September 30, 1977 interim report to the president and the congress on a comprehensive study of compensatory education.

This report surveys difficulties in establishing valid estimates concerning the cost of federal regulations.

A single-laboratory evaluation and an interlaboratory collaborative study were made of a method for determining plutonium in water. The method was written for the analysis of one-liter samples and involves coprecipitation, acid dissolution, anion exchange, electrodeposition, and alpha pulse height analysis. After the single-laboratory evaluation of the selected method, four samples were prepared for the collaborative study: two river-water samples, a substitute ocean water sample, and sample containing sediment. These samples contained plutonium-239 and plutonium-238 at concentrations ranging from 0.42 to 28.9 dis/min/liter. In the collaborative study standard deviations of plutonium concentrations ranged from 5 to 13%. In three cases, standard deviations agreed with those expected from counting statistics. It is believed that hydrolysis occurred in the river water samples resulting in errors greater than those expected from counting statistics.