The theory and a mathematical treatment of various stage-type isotope separation methods are presented. (TFD)

The study showed that the Geothermal Loan Guaranty Program has had only a negligible effect on geothermal development and the response to the program was far less than expected. The streamlining of environmental regulations and leasing policies, and the granting of intangible drilling cost write-offs and depletion allowances to operators would have had a greater impact on geothermal energy development. The loan guaranty program did not promote the undertaking of any new projects that would not have been undertaken without it. The program only accelerated the pace for some development which might have commenced in the future. Included in the study are recommendations for improving the operation of the program thereby increasing its attractiveness to potential applicants.

This LTR contains the original results of the Railroad Locomotive Tractive Effort Test performed by Kaiser Engineers on July 29, 1965, using an existing 24-wheel 500-ton dolly and the existing shielded locomotive. The test was conducted to confirm calculations of the tractive effort required to move the LOFT dolly (MTA) through the four-rail high bay curve and the curve into the LOFT containment vessel.

The unusual and potentially significant selectivity behaviors exhibited by iron- and, particularly, cobalt-graphite intercalates during CO hydrogenation warrant continued investigation, using a differential/integral flow-type reactor capable of operating at elevated reaction pressure, i.e., 0 to 300 psig. Such a system will enable further characterization of these catalysts to be made in at least three important, but heretofore unexamined, areas: this will permit the rapid acquisition of such important data as comparative turnover frequencies and apparent activation energies for CO conversion. The accuracy, convenience, and flexibility of the measurements will be greatly improved with a flow-type reaction system. Measurements of deactivation properties perforce require the use of a flow reactor and cannot be meaningfully made using a closed reaction system. Particular emphasis will be placed on establishing the effects of varying pretreatment conditions on activity/selectivity responses of the graphitic materials compared to their supported homologs. Additional information about catalyst coking properties and consequent mass balances will also be obtainable from such experiments. The most important information accessible by an elevated-pressure flow reactor are the comparative dependences of product selectivities on reaction pressure for both pairs of catalysts. In view of the already greater tendency of iron- and cobalt-graphite catalysts to produce …

A reference conceptual flowsheet based on existing or developing technology for encapsulation of stabilized calcine pellets is discussed. Conclusions and recommendations are presented.

Subassembly XX08 is a fueled and instrumented subassembly designed primarily for an ongoing program to investigate the thermal-hydraulic core environment within EBR-II under normal and off-normal plant operating conditions. XX08 contains 58-xenon-tagged, EBR-II Mark-II driver-fuel elements. The Mark-II fuel is expected to provide XX08 with an irradiation lifetime three times as great as that attained with its predecessor, XX07, i.e., a 9 versus 2.9% burnup. A burnup of 9 at.% is equivalent to about 29,000 MWt dyays of EBR-II reactor operation, which corresponds to 11 reactor runs at 2700 MWd per run.

Postirradiation examinations were performed on five fuel pins from the Gas-Cooled Fast-Breeder Reactor F-1 experiment irradiated in EBR-II to a peak burnup of approximately 5.5 at. %. These encapsulated fuel pins were irradiated at peak-power linear ratings from approximately 13 to 15 kW/ft and peak cladding inside diameter temperatures from approximately 625 to 760°C. The maximum diametral change that occurred during irradiation was 0.2% .delta.D/D₀. The maximum fuel-cladding chemical interaction depth was 2.6 mils in fuel pin G-1 and 1 mil or less in the other three pins examined destructively. Significant migration of the volatile fission products occurred axially to the fuel-blanket interfaces. The postirradiation examination data indicate that fuel melted at the inner surface of the annular fuel pellets in the two highest power rating fuel pins, but little axial movement of fuel occurred.

The transient calorimetric technique is used to measure the temperature dependence of the total hemispherical emittance of polished copper, solar selective thin films on copper and a solar selective thin film on a metal film on quartz. Experimental results on copper do not agree with the predictions of the Davisson and Weeks theory. A new theory of the emissivity of metals based on the Drude Free Electron model is developed and compared with the expermental data on copper. With no adjustable parameters, good agreement between this theory and experiment is obtained.

The coordination study of 1972 performed by Mr. N.A. Williams of Kaiser Engineers (LTR 13 10-3) is examined and updated based upon 1977 loads. Present overcurrent relay settings are presented and evaluated for adequacy in terms of the updated short circuit analysis. Recommendations are made for new relay and trip device settings to improve coordination. Switchgear ratings are examined against available short circuit currents, and recommendations are made where applicable. Vital MCC-A and B are examined in detail to provide maximum continuity of service for every fault contingency. A recommendation is made to improve the reliability of these buses.

Control of temperature swings is a major consideration in design of passive solar heated buildings - especially so as the designer seeks to achieve most of the building heat from the sun. Observations of temperature swings in several passive buildings are cited. Methods of temperature control are discussed, both by means of control intervention such as using of auxiliary backup heating, ventilation, and blowers, and by means of building design. The design approach is preferred as the main course with the intervention techniques used for fine tuning.

The levels of and underlying bases for public support, opposition, and ambivalence toward continued nuclear power development are reviewed. Data are presented on the public's general evaluations of nuclear power by indicating the extent of support and opposition, by discussing the interpretation of undecided responses, and by examining changes in public opinion over time. Differences in general attitudes toward nuclear energy related to demographic characteristics, including sex, age, education, income, and geographic region are examined. Bases for explaining public support of and opposition to nuclear power are discussed by identifying consistent patterns of attitudes among pronuclear individuals and among antinuclear individuals in the general public.

A water quality monitoring program of the Hawaii Geothermal Project well A (HGP-A) was conducted for downhole depth samples and continuous discharge samples in 1976 to 1977. The well water was slightly saline (about 5 to 10 percent ocean water) and nearly depleted of magnesium, but contained high concentrations of silica and sulfide. The chemical composition of the well water did not vary much with depth even though the sampling reached the well bottom (approximately 1768 m (5800 feet) below sea level). The well fluid temperature was higher than that of any Hawaii ground water; a maximum of 358/sup 0/C (676/sup 0/F) was recorded at the bottom of the well. The water was low in tritium but unexpectedly high in carbon-14 when compared with the surrounding ground water (sampled as cose as approx. 1609 km (1 mile) away). Mass balance calculations involving carbon and its isotopes are consistent with a model proposing that 13 percent of recharge is from sea water. During continuous flow tests, the total well yield was 83,400 lb of steam per hour, equivalent to approx. 150 gpm with 70 percent steam and the rest water. For most constituents measured, there was a one to three day …

TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothetical loss-of-flow accident. Fuel and fuel-boundary conditions in an LMFBR subassembly following sodium voiding and dryout under loss-of-flow conditions are simulated in each F-series test. Simulation is achieved with a single fuel element surrounded by an annular nuclear-heated wall in a dry (no sodium) test capsule. The area inside the heated wall was selected to represent the area inside the perimeter of an LMFBR coolant channel. Test F1 was conducted with an irradiated fuel element to investigate the effect of fission gas on fuel motion at design power levels following cladding melting and drainage. The principal conclusion from Test F1 is that fission products retarded, but did not prevent, eventual fuel collapse. The collapse was retarded by a fuel/fission-product froth that prevented fuel collapse until the fission products separated from the partially molten fuel. The fuel motion observed in F1 represents a particular type of fuel (burnup of 2.35 at.%, power rating of 394 W/cm) transient heated at design power rating.

A nondestructive autoradiographic method is described which can provide a verification that rods in the interior of unirradiated LWR fuel assemblies contain low-enriched uranium. Sufficient absorber must be used to reduce contributions to image density by beta radiation from uranium-238 daughters. When appropriate absorbers are used, the density of the image of a uranium-containing fuel rod is proportional to the uranium-235 enrichment in that rod. Exposure times as short as 1.5 hours can be achieved by using fast film and intensifying screens. Methods are discussed for reducing contributions to the image density of any single rod from radiation produced by all other rods in the assembly. The technique is useful for detecting missing rods, dummy rods, and rods containing depleted uranium. These defects can be detected by visual inspection of the autoradiographs. In its present state of development, the technique is not sensitive enough to reliably detect the difference between the various uranium-235 enrichments encountered in current BWR fuel assemblies. Results are presented for field tests of the technique at BWR and PWR facilities.

This Gruy Federal Type II-B, geopressured-geothermal (Geo) prospect was drilled as the Sun Oil Company, No. 2 Alice C. Plantation and is located in Section 2, Township 16-S, Range 10-E, St. mary Parish, Louisiana. The well site is 3,705.61 feet from U.S.C. and G.S. marker ''Foster''. The well site is located in a sugar cane field, and is accessible by approximately 2,500 feet of cane field road. The well was originally drilled to a depth of 19,000 feet and abandoned as a dry hole in December, 1963. The location is shown on the west central area of the USGS topographic sheet, 'North Bend'', Louisiana, in the Gruy Federal report, ''Investigation and Evaluation of Geopressured-Geothermal Wells, prospective Test Wells in the Texas and Louisiana Gulf Coast'', March 20, 1978.

The results of a radiological survey of the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, are presented. During the period 1940 to 1948, this site was used for the separation of UO/sub 2/ from uranium ores and for the conversion of UO/sub 2/ to UF/sub 4/. Five buildings were involved in these operations. The survey included measurements of the following: residual alpha and beta-gamma contamination levels in these buildings; external gamma radiation levels at one meter above the surface in these buildings and outdoors throughout the Linde property; radon and radon daughter concentrations in the air in these buildings; uranium, radium, actinium, and thorium concentrations in soil samples taken both onsite and offsite; contamination in surface water on and near the site; and airborne concentrations of uranium, radium, and thorium in the building in which the separation process was carried out. Elevated concentrations of uranium, radium, and/or actinium were found in two of the buildings and outdoors in widely separated areas of the site. Alpha and beta-gamma contamination levels in some areas of the buildings were above limits set by current federal guidelines concerning the release of property for unrestricted use. Elevated external gamma radiation levels …

Objective is the qualification of a PLBR-size primary loop flexible piping joint to the ASME Band PVC rules. Progress and activities are reported for: Class 1 flexible joint code approval support, engineering and design, material development, component testing, and manufacturing development. (DLC)

Atomics International and Lawrence Livermore Laboratory are involved in the conceptual design of a laser fusion power plant incorporating the lithium fall target chamber. In this paper we discuss some of the more important design considerations for the target chamber and evaluate its nuclear performance. Sizing and configuration of the fall, hydraulic effects, and mechanical design considerations are addressed. The nuclear aspects examined include tritium breeding, energy deposition, and radiation damage.

The objective of this project is the development of a preliminary design for a full-sized, closed cycle, ammonia power system module for the 100 MWe OTEC Demonstration Plant. In turn, this Demonstration Plant is to demonstrate, by 1984, the operation and performance of an ocean thermal power plant having sufficiently advanced heat exchanger design to project economic viability for commercial utilization in the late 1980's and beyond. Included in this power system development are the preliminary designs for a proof-of-concept pilot plant and test article heat exchangers which are scaled in such a manner as to support a logically sequential, relatively low-cost development of the full-scale power system module. The conceptual designs are presented for the Demonstration Plant power module, the proof-of-concept pilot plant, and for a pair of test article heat exchangers. Costs associated with the design, development, fabrication, checkout, delivery, installation, and operation are included. The accompanying design and producibility studies on the full-scale power system module project the performance/economics for the commercial plant. This section of the report describes the full-size power system module, and summarizes the design parameters and associated costs for the Demonstration Plant module (prototype) and projects costs for commercial plants in production. The …

Objectives are to assess the feasibility of macro-encapsulated PCM's for residential solar systems and to develop and evaluate such materials. Encapuslant materials under consideration are multilayer flexible plastic films, steel cans, and plastic bottls. Studies of the storage capability of CaCl/sub 2/ 6H/sub 2/O encapsulated in polyethylene bottles and Mg(NO/sub 3/)/sub 2/6H/sub 2/O/NH/sub 4/NO/sub 3/ eutectic, encapsulated in flexible plastic film packages.

Calculations indicate that the benefits of photovoltaic generation are unlikely to be soon realized unless the photovoltaic alternative is supported, as other energy technologies have been, by some sort of economic subsidy. This report describes the results of a preliminary investigation of one way of providing the required subsidy: simply allowing the utility company to recover the additional cost of photovoltaic generation through increases in charges to customers. As is shown, a very substantial early penetration of photovoltaic generation capacity into the generation mix of a utility system could be financed by quite modest increases in the annual electric bills of consumers. The analysis procedure used assumes a photovoltaic plant deployment rate and computes the total additional cost of electricity generation that would result from the deployment of the photovoltaic plants rather than of equivalent fossil-fuel plants. This additional annual cost is then apportioned, on a per kWh basis, among all utility customers, and the impact on the average residential customer's electric bill is determined.

A summary of the results of recent studies sponsored by DOE and dealing with potential photovoltaic terrestrial solar energy systems markets is presented. Quantitative data developed by these studies are summarized to assist in planning test and applications programs and in estimating the level of photovoltaic system production capacity required to meet future market needs. Near-term (1976-1985) and mid-term (1986-2000) markets are discussed.

A research program is proposed to determine the response of desert ecosystems to the operation of various solar conversion systems. Existing solar powered irrigation pumping systems are described, as well as the 5 MW solar thermal test system at Albuquerque, the proposed 10 MW central receiver system at Barstow, and photovoltaic solar dispersed power systems. The theoretical ecological impacts of solar conversion system are described. Three major impact categories are discussed in detail: shading, wind deflection, and physical disturbance. Research needs necessary to evaluate biotic and abiotic changes in the desert ecosystem are delineated, and specific monitoring and manipulation programs for existing and proposed solar conversion sites are proposed.

The existing documentation on the Geysers Unit 16 and Geysers to Lakeville transmission line projects is reviewed and data deficiencies and areas requiring clarification for filing a Notice of Intention on these projects are identified. (MHR)