Results of a preliminary design study for a solar-powered irrigation facility to be located on a farm between Phoenix and Tucson, Arizona, are presented. The ERDA-specified generic design criteria are detailed. A detailed systems analysis is presented, and preliminary designs of the thermal storage system, organic Rankine cycle power system, cooling water system, power distribution system, and collector foundation are given. Site layout and improvements are described, and a cost analysis of prototype and production units is included. Engineering drawings are included. (WHK)

This preliminary safety analysis report is based on a proposed Federal Repository at Lyons, Kansas, for receiving, handling, and depositing radioactive solid wastes in bedded salt during the remainder of this century. The safety analysis applies to a hypothetical site in central Kansas identical to the Lyons site, except that it is free of nearby salt solution-mining operations and bore holes that cannot be plugged to Repository specifications. This PSAR contains much information that also appears in the conceptual design report. Much of the geological-hydrological information was gathered in the Lyons area. This report is organized in 16 sections: considerations leading to the proposed Repository, design requirements and criteria, a description of the Lyons site and its environs, land improvements, support facilities, utilities, different impacts of Repository operations, safety analysis, design confirmation program, operational management, requirements for eventually decommissioning the facility, design criteria for protection from severe natural events, and the proposed program of experimental investigations. (DLC)

An access system based on the one now in operation at the CERN ISR is recommended. Access doors would presumably be located at the entrances to the utility tunnels connecting the support buildings with the ring. Persons requesting access would insert an identity card into a scanner to activate the system. The request would be autologged, the keybank adjacent to the door would be unlocked and ISABELLE operations would be notified. The operator would then select the door, activating a TV-audio link. The person requesting entry would draw a key from the bank, show it and his film badge to the operator who would enable the door release.

In the manufacturing process for hexanitroazobenzene (HNAB), the final step prior to heat treatment is a recrystallization of HNAB from an acetonitrile/tetrachlorethane mixture. The possibility that the above solvents might become unavailable at some future date and the toxicities of these solvents indicate a need for a new solvent system. Initial work using acetone/hexane in place of acetonitrite/tetrachloroethane indicated its feasibility (D. M. O'Keefe, Sandia Laboratories, Private Communication). The objective of the present work was to confirm the feasibility of the use of acetone/hexane system and then to scale-up the recrystallization to the size and type of equipment used in the manufacturing process. A 7.2 kg batch of HNAB was produced with the final recrystallization from the acetone/hexane system. The analysis of the HNAB-II compared favorably with that from the production process. A 50 g sample was furnished to Sandia Laboratory.

This report describes advanced fuel cell research and development activities at Argonne National Laboratory (ANL) during the period April--June 1977. These efforts have been directed toward understanding and improvement of molten-carbonate-electrolyte fuel cells operating at temperatures near 923 K. A primary focus of the work has been on developing electrolyte structures which have high strength and conductivity, as well as good electrolyte retention, and on developing methods of synthesis for electrolyte structures that are amenable to mass production. A low temperature synthesis which produces material having rodlike particles of ..beta..--LiAlO/sub 2/ has been refined and is now used for preparing electrolytes. Cell testing is essential for understanding and evaluating individual component behavior and the interactions of the components under realistic operating conditions. Most of the testing to date has been conducted in a 7-cm (2/sup 3///sub 4/-in.)-dia cylindrical cell with Type 316 stainless steel housings and current collectors, a nickel anode, and a nickel oxide cathode. Testing has begun to probe the roles of anode, cathode, and electrolyte in cell performance, and has provided verification of an acceptable technique for prevention of seal corrosion for at least 1400 hours. Components evaluation and development include post-test analysis and evaluation of cell …

It is anticipated that by employing high temperature, high pressure air to inject fuel into the combustion chamber of a diesel engine, the combustion process can be improved significantly. Better combustion should lead to better fuel economy, lower emissions of nitrogen oxides and unburnt hydrocarbons, less smoke, less noxious odors, reduced noise, less vibrations, increased power per unit weight of the engine, improved cold starting capability and engine operation with a wider range of fuels. The program involves development, design, fabrication and breadboard testing of an air assisted fuel injector for a single cylinder diesel engine. The experiments are to be guided by an analytical combustion study based on a stochastic model of turbulent mixing with chemical reactions. Progress is reported. (WHK)

Two sample changers are described that were designed for liquid scintillation counting of alpha-emitting samples prepared using solvent-extraction chemistry. One operates manually but changes samples without exposing the photomultiplier tube to light, allowing the high voltage to remain on for improved stability. The other is capable of automatically counting up to 39 samples. An electronic control for the automatic sample changer is also described.

A general description is provided of electrical transmission systems as an aid in determining their environmental impacts. Alternating current, direct current, overhead systems, underground systems, and water crossings are treated. The cost, performance, reliability, safety, and environmental impact of these systems are compared.

The report discusses and evaluates the adequacy of buyer specifications for snubbers. Technical specifications for snubbers (hydraulic and mechanical) were studied in detail in an effort to define the ''fundamental needs'' of the industry with respect to characteristics of snubbers during operation. In the course of this study, it was determined that there is insufficient consensus among users to make such a definition. Authorities in the fields of structural dynamics, structural systems design, and snubber design were also consulted for additional information. Information from these sources is incorporated to identify the fundamental areas of concern, areas where consensus is lacking, and problems to be resolved in order to establish meaningful standards for this equipment.

Test S-02-6 of the Semiscale Mod-1 blowdown heat transfer test series was conducted to supply data for the U.S. Nuclear Regulatory Commission Standard Problem Six. To determine the credibility of the data and thus establish the validity of Standard Problem Six, an analysis of the results of Test S-02-6 was performed and is presented. This analysis consisted of investigations of system hydraulic and core thermal data. The credibility of the system hydraulic data was investigated through comparisons of the data with data and calculations from related sources (Test S-02-4) and, when necessary, through assessment of physical events. The credibility of the core thermal data was based on a thorough analysis of physical events. The results of these investigations substantiate the validity of Test S-02-6 data.

The Harwell Boron Pile measurement of the average number of prompt neutrons emitted per fission, ..nu..-bar/sub p/, of /sup 252/Cf was analyzed in detail by a Monte Carlo method. From the calculated energy dependence of the neutron detection efficiency a value of ..nu..-bar/sub p/ = 3.733 +- 0.022 was obtained. This value is 0.76 percent higher than the original reported value of 3.705 +- 0.015. Possible causes for this increase are discussed. 3 figures, 6 tables.

On April 14, 1976, EG and G performed the Semiscale Blowdown 29-1 experiment to try to establish the feasibility of using a transit time flowmeter (TTF) to measure transient blowdown two-phase flow rates. The recorded signals from that experiment were made available to and analyzed by the Argonne National Laboratory using the transfer function cross-correlation technique. The theoretical background for the transfer function method of analysis and the results of the data analysis are presented. Histograms of transit time during the blowdown are shown and topics for further investigation are identified.

The constraints and phenomena which must be modeled in realizing a rational prediction of temperature history in a radioactive waste repository are presented. The effects of conductive and radiative heat transfer between the waste package and host rock are presented. Results of numerical investigations are utilized to present specific situations wherein analytical approximations to the waste canister geometry may be utilized. The paper also presents the results of approximations to the mean underground repository temperatures. The reliability of both methods of predicting temperatures is assessed through the comparison of predicted temperatures with measured temperatures from the Project Salt Vault field experiment. The design of experiments for model verification is discussed and a specific heater experiment which has been proposed is presented.

This bibliography contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at boiling-water reactor nuclear power plants in 1976. The report includes 1,253 abstracts that describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. They are arranged alphabetically by reactor name and then chronologically for each reactor. Key-word and permuted-title indexes are provided to facilitate location of the subjects of interest, and tables that summarize the information contained in the bibliography are provided. The information listed in the tables includes instrument failures, equipment failures, system failures, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction). Three of the unique events that occurred during the year are reviewed in detail.

The bibliography contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at pressurized-water reactor nuclear power plants in 1976. Included are 1264 abstracts that describe incidents, failures, and design construction deficiencies experienced at the facilities. They are arranged alphabetically by reactor name and then chronologically for each reactor. Key-word and permuted-title indexes are provided to facilitate location of the subjects of interest, and tables summarizing the information contained in the bibliography are presented. The information listed in the tables includes instrument failures, equipment failures, system failures, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction). A few of the unique events that occurred during the year are reviewed in detail.

This report talks about the annual progress report of 1977

Due to the strong localization of the fusion born ..cap alpha..-particles in velocity and configuration space and their coupling to Alfven waves in the background plasma the relaxation of ..cap alpha..-s is anomalous. In a finite system, the enhanced electromagnetic fluctuations can produce rapid spatial losses of ..cap alpha..-population and energy. These losses prevent the ..cap alpha..-velocity distribution from attaining a stable collisional equilibrium, thus maintaining a steady state turbulence level. A self-consistent numerical quasilinear calculation is performed for the most dominant mode, showing the evolution of the ..cap alpha..-distribution and yielding the anomalous loss rates.

Progress is reported in the following areas of research: personnel monitoring; health physics instrumentation; atmospheric monitoring; water monitoring; radiation background measurements; soil samples; laboratory operations monitoring; radiation incidents; laundry monitoring; accident analysis; and industrial safety. (HLW)

An approximate correction for finite material temperature and boundary motion is presented for elastic scattering energy depositions.

This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection. (RWR)

A review and assessment is made of the Hanford low level solid radioactive waste management sites and facilities. Site factors considered favorable for waste storage and disposal are (1) limited precipitation, (2) a high deficiency of moisture in the underlying sediments (3) great depth to water table, all of which minimize radionuclide migration by water transport, and (4) high sorbtive capacity of the sediments. Facilities are in place for 20 year retrievable storage of transuranic (TRU) wastes and for disposal of nontransuranic radioactive wastes. Auxiliary facilities and services (utilities, roads, fire protection, shops, etc.) are considered adequate. Support staffs such as engineering, radiation monitoring, personnel services, etc., are available and are shared with other operational programs. The site and associated facilities are considered well suited for solid radioactive waste storage operations. However, recommendations are made for study programs to improve containment, waste package storage life, land use economy, retrievability and security of TRU wastes.

Results are reported from measurements of present radionuclide concentrations in Columbia River sediments. A description of the rates and mechanisms governing the decrease in radioactivity levels in the river sediments between 1971 and 1976; a characterization of the areal and depth distribution of fine grain, silty sediments in the McNary Reservoir mode by sub-bottom seismic surveying; and analysis of deep piston cores which penetrate the entire thickness of sediment deposits at selected sites in McNary Reservoir to provide radionuclide data for estimating the inventories of radionuclides in the sediment deposits in the McNary Reservoir are included. The results of these studies showed that the short- and intermediate-lived radionuclides have now decayed to insignificant levels, and only a few long-lived radionuclides (i.e., /sup 54/Mn, /sup 55/Fe, /sup 60/Co, /sup 137/Cs, /sup 152 -154/Eu, /sup 238/Pu, /sup 239 -240/Pu, and /sup 241/Am) at trace concentrations remain buried in the sediment deposits. The surface sediments in the McNary Reservoir contain much lower radionuclide concentrations than deeper sediments because of the build-up of 40 to 80 cm of fresh, relatively uncontaminated new sediment deposits since 1971.

The astrophysical elements opacity library includes equation of state data, various mean opacities, and 2000 values of the frequency-dependent extinction coefficients in equally spaced intervals u identical with h..nu../kT from 0 to 20 for 41 degeneracy parameters eta from -28 (nondegenerate) to 500 and 46 temperatures kT from 1 eV to 100 keV. Among available auxiliary quantities are the free electron density, mass density, and plasma cutoff frequency. A library-associated program can produce opacities for mixtures with up to 20 astrophysically abundant constituent elements at 4 levels of utility for the user.

This quarterly report is the fifth in a series intended to provide information on research and engineering activities being performed to improve the processing of irradiated reactor fuels, the production of plutonium, and the management of resultant chemical wastes.