Specifications, operation, characteristics, cost, and experience with the NAL 15-ft bubble chamber are described. Beam availability and some experimental proposals are discussed. (WHK)

This program consists of a design study and component development for an experimental 50-kWp photovoltaic concentrator system to supply power to the San Ramon substation of the Pacific Gas and Electric Company. The photovoltaic system is optimized to produce peaking power to relieve the air conditioning load on the PG and E system during summer afternoons; and would therefore displace oil-fired power generation capacity. No electrical storage is required. The experiment would use GaAs concentrator cells with point-focus fresnel lenses operating at 400X, in independent tracking arrays of 440 cells each, generating 3.8 kWp. Fourteen arrays, each 9 feet by 33 feet, are connected electrically in series to generate the 50 kWp. The high conversion efficiency possible with GaAs concentrator cells results in a projected annual average system efficiency (AC electric power output to sunlight input) of better than 15%. The capability of GaAs cells for high temperature operation made possible the design of a total energy option, whereby thermal power from selected arrays could be used to heat and cool the control center for the installation. System design and analysis, fabrication and installation, environmental assessment, and cost projections are described in detail. (WHK)

The faciliies described will provide a direct route from the 241-S-151 and 241-U-151 Diversion Boxes to the 241-SY Tanks. The 244-S Catch Station will consist of a 20,000 gallon primary tank contained within a concrete vault lined with carbon steel. Encased three-inch carbon steel process lines will be extended to the catch station pump pit from the 241-SY Tank Farm, the 241-S-151 Diversion Box and the 241-U-151 Diversion Box encasement. The facility will have its own ventilation system for exhausting the primary tank and the annulus area. A small instrument shack will house locally mounted instrumentation and controls. Existing designs for Project B-103 will be used where similarities exist (H-2-38200). The project is expected to cost $1,900,000 and require 19 months for the initiation of Title I design until construction is complete.

The Energy System Network Simulator (ESNS) flow model is installed on the Brookhaven National Laboratory (BNL) CDC 7600/6600 computer facility for access by off-site users. The method of access available to outside users is through a system called CDC-INTERCOM, which allows communication between the BNL machines and remote teletype terminals. This write-up gives a brief description of INTERCOM for users unfamiliar with this system and a step-by-step guide to using INTERCOM in order to access ESNS.

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Present techniques for measuring sound velocity in liquid metals have been limited by the use of transducers which cannot survive in extreme temperature conditions. These methods also require relatively long measurement times. An optical noncontacting method has been developed which may be used for extremely short experimental times and very high temperatures and pressures. This technique is being incorporated into an isobaric expansion apparatus in which a 1 mm diam wire sample in a high pressure argon gas environment is resistively heated to melt within a time period of only a few microseconds. Before instability of the liquid column occurs, thermal expansion, enthalpy, and temperature are measured. The addition of the sound velocity measurement permits a more complete determination of the thermophysical properties of the liquid metal.

Actinide cross section data at thermonuclear neutron energies are needed for the calculation of ICF pellet center burnup of fission reactor waste, viz. 14 MeV neutron fission of the very long-lived actinides that pose storage problems. A major advantage of pellet center burnup is safety: only milligrams of highly toxic and active material need to be present in the fusion chamber, whereas blanket burnup requires the continued presence of tons of actinides in a small volume. The actinide data tables required for Monte Carlo calculations of the burnup of /sup 241/Am and /sup 243/Am are discussed in connection with typical burnup reactor fusion and fission spectra. 2 figures.

Comparison of the 1978 projections of the Reliability Councils with those made the previous year indicates three major changes in electric utility planning: (1) a reduction in total capacity additions for the 10-year planning period, (2) a significant decrease in nuclear additions, and (3) a shift from oil and gas to coal as a source of primary energy. Nuclear capacity continues to far overshadow fossil-fuel capacity in the unit-size range 1000 MW and up, with the reverse true for unit sizes less than 1000 MW. Although the total 10-year new-unit capacity drops from 326,624 MW (1977 to 1986) to 308,017 (1978 to 1987), new capacity planned that would use coal as a primary energy source increases from 136,763 MW to 146,206 MW. Nuclear capacity, in terms of total new units projected for the two 10-year periods, decreases from 130,532 MW to 116,177 MW, and capacity with oil as the primary source drops from 32,837 MW to 21,072 MW. For 1977 to 1986, no capacity was planned with oil as a primary source and coal as an alternate fuel but for 1978 to 1987, 1220 MW of such capacity is projected. Therefore, the total new capacity projected that could use coal …

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The concept design for a small (less than 10 MWe) solar thermal electric generating plant was completed using projected 1985 technology. The systems requirements were defined and specified. The components, including an engineering prototype for one 15 kWe module of the generating plant, were conceptually designed. Significant features of the small solar thermal power plant were identified as the following: (1) 15-kWe Stirling-cycle engine/alternator with constant power output; (2) 10-meter point-focusing paraboloidal concentrator with cantilevered cellular glass reflecting panels; (3) primary heat pipe with 800/sup 0/C output solar cavity receiver; (4) secondary heat pipe with molten salt thermal energy storage unit; (5) electric energy transport system; and (6) advanced battery energy storage capability. The present emphasis for achieving cost reduction goals centers on improving conversion efficiency and reducing the cost of key components.

Final report documenting a high-sensitivity airborne gamma radiation and magnetic field survey of the Baker National Topographic Map segment (NL 11-11 quadrangle) including a description of the program and results.

The following report is the first of two volumes describing the program and results of the airborne gamma and total magnetic field surveys of the Reno quadrangle conducted between October 4-November 10, 1977.

From Operational Program: This final report includes a general geologic description of the area, including descriptions of the various geologic units and correlates the airborne data to the geologic units as provided by the geologic maps. Also included is a frequency distribution study of the data as a function of the geologic units encountered over the NTMS area including the tie line data.

Final report documenting a high-sensitivity airborne gamma radiation and magnetic field survey of the Walker Lake National Topographic Map segment (NJ 11-4 quadrangle) including a description of the program and results.

This report presents some statistics and trends that indicate alcohol use is a a problem that merits Congressional attention as a public health program.

This report describes circumstances involved in the alleged 91.2 grams of plutonium released to the 216-Z-19 Ditch from the 231-Z facility. The following areas were reviewed: 231-Z liquid waste data collected by Battelle-Northwest and Rockwell Hanford Operations (Rockwell); the sampling methods used by Battelle and Rockwell; and operating conditions in the 231-Z and 234-5Z Buildings at the time of the alleged release.

ASTM mechanical property specification verification tests have been conducted on the 2 /sup 1///sub 4/ Cr--1 Mo steel. The base properties have been determined for the steel at various temperatures and after exposure to various environments. Compression load versus deflection calibration curves have been determined for 316 SS loading rings. Thermal expansivity of both the 2 /sup 1///sub 4/ Cr--1 Mo steel and 316 SS have been determined at 500/sup 0/F and 900/sup 0/F. Thermal expansion characteristics and time dependence of the deflection of ring-sample composites have been measured to provide information about the constancy of stress on samples loaded by pre-compressed rings. Results of all exposure tests, including samples under load during exposure, in inert gas reveal that no degradation of ambient temperature mechanical properties occurs.

ASTM mechanical property specification verification tests have been conducted on the 2 /sup 1///sub 4/ Cr--1 Mo steel. The base properties have been determined for the steel and calibrations on the thermal expansivity of both the 2 /sup 1///sub 4/ Cr--1 Mo steel and 316 SS for use as loading rings have been completed.

The objective of this program is to evaluate the mechanical properties of liquefaction process plant ''dissolver'' vessel materials in a ''dissolver'' vessel environment including coal slurry and pressurized hydrogen gas at temperatures up to 900/sup 0/F. Specifically, the degradation of notched-bar and smooth bar tensile samples of 2/sup 1///sub 4/ Cr--1 Mo will be monitored as a function of exposure time and stress in the ''dissolver'' vessel environment. This quarter was spent entirely on installing and debugging the newly acquired pressure vessels and their controlling circuitry. The vessels were installed in the Ames Lab explosion-safe, hydrogen-containment building, specially designed for this program. Leak checks of 24 to 72 hours were performed on the vessels at pressures ranging from 1000 to 5000 psig at temperatures of 72/sup 0/F and 800/sup 0/F. Automatic pressure and temperature monitoring controls were tested and calibrated. Pressure vessel furnaces were installed and are being tested. Containment building safety systems including hydrogen detectors, vessel over-pressure alarms, vessel over-temperature alarms, hydrogen check valves, surge valves, power failure emergency backup systems and fire alarms were tested and found satisfactory. Individual pressure vessel containment cell blow out panels and cell ventilation systems were found to be satisfactory.

ASTM mechanical property specification verification tests have been conducted on the 2 /sup 1///sub 4/ Cr-1 Mo steel. The base properties have been determined for the steel and calibrations on the thermal expansivity of both the 2 /sup 1///sub 4/ Cr-1 Mo steel and 316 SS for use as loading rings have been completed.

Base properties have been determined for A387-74A-Gr. 22-Cl. 2 steel at various temperatures in inert environments. Tests have been completed to monitor the actual stress level as a function of exposure time in tensile samples loaded in pre-compressed rings. Samples were exposed under various stress levels at 900/sup 0/F to determine the amount of creep during the 168 hour exposures. Results of all exposure tests (including samples under load during exposure with and without creep, in inert gas) revealed that no degradation of ambient temperature mechanical properties occurred.

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Measurements of the voltage and currcnt that resulted from a quench of a superconducting magnet were studied and a simple computer model of this process was developed. Large layer-tolayer voltages were generated by the quench and methods reducing these were suggested and examined. (auth)

This report is an analysis of cost factors of 1974 coal prices.