The exposures of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a ..beta.. dose of 10 ..mu..Ci/cm/sup 3/, a ..gamma.. dose of 10/sup -5/ ..mu..Ci/cm/sup 3/, and an ..cap alpha.. dose of 4.9 x 10/sup -3/ ..mu..Ci/cm/sup 3/ were completed. Exposure to ..beta.. and ..gamma.. radiation did not affect membrane performance. After a simulated six months of exposure to ..cap alpha.. radiation some degradation of membrane performance occurred. Several experiments were made on a laboratory-scale reverse-osmosis unit using the product from ultrafiltration as feed. Rejection of activity ranged from 88 to 99 percent. The ''continuous'' ultrafiltration pilot run was completed. Approximately 40,000 gal were processed in over 70 hr of operating time without shutdown for cleaning. Flux and rejection were maintained relatively steady over this period. Rejection of gross alpha ranged from 80 to 99.5 percent depending on the ionic content of the waste stream. Flux rates ranged from 5 to 8 liters/min over this period. The engineering column tests were continued using uranium-233 with product from the ultrafiltration pilot plant. Flow rates and pH were varied in order to determine optimum operating conditions.

The proposed Goose River Project is a commercial power development consisting of 4 power dams and one storage dam. All available energy is to be wholesaled to the Central Maine Power Company, the utility holding the franchise for the area. A description of the economic feasibility of the proposed project is presented.

The purpose of this analysis was the calculation of stresses in the LOFT Containment Vessel at the point of nozzle penetration produced by loads on the nozzles and to show that those stresses are within the 1965 ASME Boiler and Pressure Vessel Code allowables. The stress determination was done by the method developed by P. P. Bijlaard on the worst load case for each diameter nozzle. The operating basis earthquake (OBE) at nozzle 11D produced the most severe load case. All load cases resulted in containment vessel stresses that were less than the allowables as stated in N-414 of the 1965 ASME Boiler and Pressure Vessel Code.

Normal incident solar energy measurements made at Upton, L.I., New York are reported and analyzed relative to the total energy received on a horizontal surface. A new method for computing normal incident solar radiation is developed and used to study long term variations in this energy source at Upton and to estimate average values for other east coast locations.

The present archaeological survey and cultural resource assessment were conducted for the United States Department of Energy, Morgantown Energy Technology Center in areas to be disturbed by gas well drilling and holding pond construction. The project area is the Pine Creek drainage system, which is a tributary of the Ohio River in Scioto and Lawrence Counties, Ohio. The literature search indicated that prehistoric archaeological sites do occur and have been documented in the Pine Creek drainage system. Presently, no archaeological sites have been reported in locations of direct impact. The literature search also indicated that historic features from the early iron industry period, ca. 1840 to 1870, are likely to occur throughout the project area. Field reconnaissance identified three prehistoric archaeological sites and one historic site in and adjacent to the proposed locations of disturbance. Two sites were determined to be of significant research value and may be nominated to the National Register of Historic Places. Consequently, recommendations were made to minimize the adverse effects of the proposed drilling project on these archaeological sites.

This specification establishes minimum design, qualification and acceptance requirements for terrestrial solar cell modules suitable for incorporation in photovoltaic array applications in the 20kW to 500kW range, such as defined by Department of Energy PRDA EM-D-04-0038. Both mandatory and recommended requirement levels for selected performance criteria have been specified for modules within these arrays. As applicable, the manufacturer/contractor shall be responsible for generation and selection of appropriate design or test levels within the scope of these criteria. Specification of any additional requirements as necessary to satisfy the particular array or system application shall be the responsibility of the manufacturer/contractor. Environmental requirements imposed by this specification are considered to be the minimum level acceptable to DOE. Test procedures are detailed.

The ''TAN/LOFT 13.8 kV, 2.4 kV, and 480 V Relay and Circuit Breaker Coordination Study'' presented an analysis to determine overcurrent settings for the LOFT Power System protective relays including those for the drive motors of the PSMG sets. This LTR is written to form the basis of the relay settings entered in Specification ES-60238 Rev. B, for protection of the PSMG generator, primary coolant pump motor and interconnecting power cable. A momentary commercial power voltage dip occurred on January 10, 1978 which caused a trip of the PSMG field breakers. A corrective design to prevent reoccurrence is discussed and recommendations are presented.

The conduit system in the LOFT Support Building was analyzed for seismic loading. The conduit itself plus its various supports were subjected to both horizontal and vertical forces. The results show the system loads or stresses to be within allowables.

This report describes the use of a Material Control System Simulator (MCSS) program for determination of material accounting uncertainty and system response to particular adversary action sequences that constitute plausible material diversion attempts. The program is intended for use in situations where randomness, uncertainty, or interaction of adversary actions and material control system components make it difficult to assess safeguards effectiveness against particular material diversion attempts.

Reconnaissance experiments have shown that waste/basalt interactions are of real importance in understanding all aspects of total containment of radionuclides in a basalt repository. It has been shown that the reprocessed waste forms, calcine and glass, are relatively more reactive than the more crystalline waste forms, spent unreprocessed fuel (SURF) and supercalcine. These experiments have established the direction of future research. The remainder of the program will be concerned with longer-duration and more-detailed experiments whose emphasis will be on understanding the mechanisms of reaction. Long-duration and in-depth experiments are being initiated to establish kinetic relationships and get a better feel as to whether or not we are approaching equilibrium in our shorter-duration reconnaissance experiments. In some cases, especially at higher temperatures, it appears that we are approaching a steady-state wherein products are no longer changing. This, however, might be a metastable state. Experiments with cesium compounds thought to be present in SURF (Cs/sub 2/MoO/sub 4/), a simple cesium source (CsOH), labradorite, and ground water have shown that pollucite forms and, as a result, fixes 86 to 99% of the cesium (depending upon the amount of basalt present.

Research during the period is reported on interfacial phenomena, polymer rheology and fluid mechanics, thermodynamic properties, and rock/fluid interactions. (JRD)

This specification establishes minimum design, qualification and acceptance requirements for terrestrial solar cell modules suitable for incorporation in photovoltaic array applications in the 20 kW to 500 kW range, such as defined by Department of Energy PRDA EM-D-04-0038. Both mandatory and recommended requirement levels for selected performance criteria have been specified for modules within these arrays. As applicable, the manufacturer/contractor shall be responsible for generation and selection of appropriate design or test levels within the scope of these criteria. Specification of any additional requirements as necessary to satisfy the particular array or system application shall be the responsibility of the manufacturer/contractor. Environmental requirements imposed by this specification are considered to be the minimum level acceptable to DOE.

Results of work performed from July 1, 1978 through September 30, 1978 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. Candidate alloys were evaluated for Very High Temperature Reactor Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the affect of simulated reactor primary coolant (Helium containing small amounts of various other gases), the high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. The activities associated with the characterization of the materials for the screening test program are reported, i.e., test specimen preparation, information from the materials characterization tests performed by General Electric, and the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented.

A commercial 7.5-kW electron-beam welder has been optically upgraded. The viewing system has been replaced by high-resolution optics (36 line pairs per millimeter (36l/mm) with video option. A high-intensity arc lamp provides illumination of the weld region. The upgraded optical system provides the capability for making accurate and repeatable welds with computer-automated seam tracking.

Miscible-liquid displacements of water/ethanol solutions were conducted in a 2.54-cm-ID column packed with glass beads of 275 to 300 and 25 to 30 mesh with bed heights of 6.35 to 40.8 cm. The viscosity ratio of the resident fluid to displacing fluid was maintained at 0.72 for fluid pairs with favorable density differences. Dispersion coefficients obtained from a two-parameter model increased from approx.3 x 10/sup -5/ to approx.2 x 10/sup -2/ cm/sup 2//s with increasing packing particle size, fluid velocity, and density difference.

It is pointed out that corrections due to the Coulomb-nuclear interference could amount to an order of 1 to 2 mb at P/sub lab/ around 1 GeV/c in recently performed measurements of the pp-total cross section difference in pure spin states.

This report addresses the Women, Infants, and Children (WIC), which was created in 1972 as a two-year program to make supplemental foods available to pregnant and lactating women, infants, and to children who were determined by competent professionals to be nutritional risks because of inadequate income.

A description is presented of a Material Control System Simulator (MCSS) program for determination of material accounting uncertainty and system response to particular adversary action sequences that constitute plausible material diversion attempts. The program is intended for use in situations where randomness, uncertainty, or interaction of adversary actions and material control system components make it difficult to assess safeguards effectiveness against particular material diversion attempts. Although MCSS may be used independently in the design or analysis of material handling and processing systems, it has been tailored toward the determination of material accountability and the response of material control systems to adversary action sequences.

This report consists of constitutional rights of children.

This report consists the history and select bibliography of the term of office of the U.S. House of Representative members. It includes the chronology of action on length of the House terms at the Constitutional convention, efforts to alter the House term, and amendments to the Constitution lengthening the Term of Office for the U.S. House of Representatives.

This workshop was the seventh of a series and was held on October 23-24. 1978, at the Central Electricity Generating Board, HQ, London, England. Typically~ attendees at the Workshop were concerned with one of three activities: studying and refining existing techniques in an attempt to quantify already-known parameters with greater precision, looking for ways to apply existing neutron dosirr:etry techniques to a specific local problem, identifying the needs and weaknesses of existing systems, with the goal of improving and passibly simplifying field measurements. The types of neutron dosimetry techniques discussed by participants included albedo dosimeters, track etch, and TLD. One speaker reported on NTA film, noting that fading could be eliminated by drying the emulsion in dry nitrogen before field use. There were no reports on tissue equivalent proportional counters or activation analysis. One participant discussed a metal oxide silicon dosimeter. The need to develop a consistent standard terminology, as well as calibration sources and techniques, on both the national and international level was evident. The need for standardization is particularly acute in the U.S. Techniques for evaluating dosimeter response in the field should he standardized, since several different instruments with widely different response characteristics are currently being used. The …

This report is about Electronic Fund Transfers. A discussion and analysis of the national commision on electronic funds transfer's final report.

This report is a collection of tables compiled in response to a congressional request for information on the impact of United States foreign aid and defense operations on the U.S. balance of international payments.

This report is about the development of small-scale Hydroelectric power stations.