Activities during the last two months are described. A significant portion of time was spent reviewing the literature on the Cs/sub 2/O-Al/sub 2/O/sub 3/-SiO/sub 2/ system, on the use of clays and zeolites for Cs-fixation of aqueous wastes, and on silicate-phosphate apatite structure crystal chemistry. The results from the latest group of compatibility studies (CS-runs) were used to modify the first demonstration supercalcine formulation so that it is more in line with the actual crystalline phase formation. Supercalcine formuation 75-2 is described.

The results of analyses of the airborne gamma radiation and total magnetic field survey flown for the region identified as the Bozeman National Topographic Map NL12-8 are presented in Volume I and II of this report. The airborne data gathered are reduced by ground computer facilities to yield profile plots of the basic uranium, thorium, and potassium equivalent gamma radiation intensities, ratios of these intensities, aircraft altitude above the earth's surface, total gamma ray and earth's magnetic field intensity, correlated as a function of geologic units. The distribution of data within each geologic unit, for all surveyed map lines and tie lines, has been calculated and is included. Two sets of profiled data for each line are included with one set displaying the above-cited data. The second set includes only flight line magnetic field, temperature, pressure, altitude data plus magnetic field data as measured at a base station. A general description of the area, including descriptions of the various geologic units and the corresponding airborne data, is included also.

The objective of the research program is to develop and analyze new concepts for absorption cycles to improve the performance or reduce the cost (or both) of a 3-ton absorption chiller that can be used with solar-collected heat. New refrigerant-absorbent pairs, additives to currently used refrigerant-absorbent pairs, and modifications to the cycle are being investigated. For the initial analyses the use of a fluid at 160 to 230/sup 0/F from a solar collector as a heating source is assumed. In the initial analyses the chiller is to provide chilled water at 45/sup 0/F at full load; alternatively, if a new refrigerant-absorbent pair appears to be amenable for direct cooling of the occupied space, the temperature of the evaporator is to be 45/sup 0/F. Both water cooling and air cooling of the absorber and the condenser are being studied. The use of ambient air at 95/sup 0/F dry bulb and 75/sup 0/F wet bulb temperatures is assumed. With the water-cooled cycles, the initial and operating costs of a properly sized cooling tower will be included. The research consists of five principal tasks: (a) acquisition of information for analysis, (b) definition of criteria for selection of promising refrigerant-absorbent pairs, additives for currently …

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.

This report talks about the annual progress report of 1977

The kinetics of precipitation reactions in geothermal brines can be studied accurately only if the brine samples are collected and examined under anaerobic conditions and with minimum cooling. Apparatus and techniques were developed that achieve this for brine temperatures below 100/sup 0/C. The concentration of suspended solids is measured gravimetrically after filtration, and the concentration of dissolved silica is measured by atomic absorption spectrophotometry. Data from Woolsey No. 1 well of the Salton Sea Geothermal Field illustrate typical results of the procedures.

Flat plate chord tests are one experimental method used to investigate how fluid/structure interaction (FSI) effects modify the impulsive loading in nuclear reactor pressure suppression pools. This analytical study examines the applicability of using a flexible flat plate in an otherwise rigid shell to model dynamic pool wall response in a flexible shell pressure suppression torus. Bubble pressures varying by a factor of seven are used as input to two-dimensional finite-element models. Boundary response to various plate and shell thicknesses are compared on the basis of equivalent natural frequency. Results indicate the qualitative flat plate response compares well with the flexible shell but absolute pressures vary significantly and nonconservatively.

Experimental data in the literature on the physical, thermodynamic, and transport properties of aqueous LiOH are summarized. The behavior of some properties is predicted beyond the range of the data. 12 fig, 14 tables, 20 references.

An automated system for the performance of ion-exchange chromatography with corrosive solvents has been built. It is LSI-II microcomputer controlled and is capable of selecting six sample/solvents and collecting six separate fractions. Preliminary results on the separation of plutonium from 8M HNO/sub 3/ solutions indicate that the system can achieve chemical yields, analytical accuracy, and precision fully comparable to manual column operation at a considerable savings of operator time.

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Beryllium casting is a relatively new technology with the successful cast of large ingots being developed during the last decade. In 1961, Rocky Flats initiated a beryllium ingot-sheet fabrication process that included the development of new techniques to consistently cast large sound beryllium ingots. This report reviews the casting technology that was developed to cast these beryllium ingots on a production basis along with some of the remaining technical problems requiring additional development work.

The reaction of laser excited Ba*(/sup 3/D) states with nitric oxide is presented. BaO product is not detected, although the channel is thermodynamically open, and instead chemiluminescence is observed. Experiments which suggest that radiative recombination, Ba + NO ..-->.. BaNO* ..-->.. BaNO, is the observed reaction channel will also be presented.

The status of the following studies is given: calorimetry and thermodynamics of nuclear materials; americium recovery and purification; optimization of the cation exchange process for recovering americium and plutonium from molten net extraction residues; evaluation and comparison of bidentate extractants and methods for actinide recovery; a combined anion exchange-bidontate organophosphorus extraction process for molten salt extraction residues; a combined anion exchange-extraction chromatography technique for secondary recovery; plutonium recovery in the Advanced Size Reduction Facility; decontamination of Rocky Flats soil; separating lead and calcium from americium by chromate and oxalate precipitation; demonstration of the pyroredox process in the induction-heated, tilt-pour furnace; process development for recovery of americium from vacuum melt furnace crucibles; plutonium peroxide precipitation process; and a comparative study of annular and Raschig ring-filled tanks.

Consider the problem of testing goodness-of-fit to a specified location-scale family when evidence is to be combined from several independent samples, from populations with possibly different location and scale parameters. The procedure studied is that of computing standardized residuals from each sample and then combining these into one set to be treated essentially as though they came from one sample. It is shown that the limiting distribution of any location-scale invariant goodness-of-fit statistic so applied is precisely the same as for the corresponding one-sample problem. 13 references.

Large pools for storing spent fuel elements from nuclear reactors are being proposed to augment the present storage capacity of pools located at nuclear power plants and fuel reprocessing plants. These pools will be part of either independent spent fuel storage installations or large reprocessing plants. Because of the large size of the pools, seismic loads are of significant interest, and in particular the adequacy of current design methods for calculating seismic loads was of special concern. An evaluation of design methods representative of current practice was carried out, and the results are summarized. The evaluation was based on a comparison of total structural loads obtained by these methods with those obtained using the LUSH code. The LUSH code offered a combination of latest technologies in structural analysis involving soil-structure interaction.

Computer codes are used to assist the reduction of data from the LLL project assessing emissions of coal-fired power plants. Five programs, PROGE, PROGX, PROGW, FM77, and FM78, have been developed recently to sort, reduce, and display data acquired from cascade impactor samples. The data include elemental concentrations, enrichment factors, standard deviations, weighted averages, and unit conversions. The procedures required to run these programs are given in this report.

The conceptual design of a solar process steam system began with studies and evaluations of various alternative design configurations. From these evaluations a final candidate design configuration was selected which is to be used for further detailed analysis and engineering. An evaluation of various types of distributed collector systems is presented. Cost-effectiveness of various distributed collectors was determined on the basis of total relative cost (including foundation and installation) of the collector per square foot of collector surface for the same thermal output at noon. The considerations used to select the optimum site also are given. System optimization studies are presented, including a discussion of whether a storage facility should be provided. It was found that none is required. Three alternate system configurations are described, optimized, and compared and a final concept is selected in which water is partially boiled in the slat type collectors and steam is separated in a steam drum. A cost-effectiveness criterion based on the unit cost of net annual thermal energy generated was used in the optimization studies and is discussed. The impact of the system on the environment is assessed and a preliminary safety analysis is presented. (LEW)

The Emergency Core Cooling System (ECCS) for the LOFT reactor may need to be disabled for modifications or repairs of hardware or instrumentation or for component testing during periods when the reactor system is hot and pressurized, or it may be desirable to enable the ECCS to be disabled without the necessity of cooling down and depressurizing the reactor. LTR 113-47 has shown that the LOFT ECCS can be safely bypassed or disabled when the total core power does not exceed 25 kW. A modified policy involves disabling the automatic actuation of the LOFT ECCS, but still retaining the manual activation capability. Disabling of the automatic actuation can be safely utilized, without subjecting the fuel cladding to unacceptable temperatures, when the LOFT power decays to 70 kW; this power level permits a maximum delay of 20 minutes following a LOCA for the manual actuation of ECCS.

The purpose of this investigation was to determine the corrosion behavior of a high strength steel (ASTM A416-74 grade 270), typical of those used as tensioning tendons in prestressed concrete pressure vessels, in several corrosive environments and to demonstrate the protection afforded by coating the steel with either of two commercial petroleum-base greases or Portland Cement grout. In addition, the few reported incidents of prestressing steel failures in concrete pressure vessels used for containment of nuclear reactors are reviewed. The susceptibility of the steel to stress corrosion cracking and hydrogen embrittlement and its general corrosion rate were determined in several salt solutions. Wires coated with the greases and grout were soaked for long periods in the same solutions and changes in their mechanical properties were subsequently determined. All three coatings appeared to give essentially complete protection but small flaws in the grease coatings were detrimental; flaws or cracks less than 1 mm wide in the grout were without effect.

A small, secondary treatment plant for processing sanitary wastes was upgraded by the addition of tertiary treatment (chemical treatment and final clarification) and mixed-media filtration. Operational data showed that the tertiary treatment significantly reduced pollutants. Filtration further reduced suspended solids significantly and removed some additional phosphorus; however, no additional reduction in total oxygen demand or in nitrogen was noted. Detailed analyses of costs for construction and routine operations showed the cost of tertiary treatment was small compared to costs associated with mixed-media filtration.

The cryocondensation pumping system for the TFTR neutral beam injectors is described. Topics include hardware design, differential pumping and beam loss, operational modes, and response to massive vacuum breaks.

Detailed estimates shown for the respective states are based largely on existing contracts and grants which are assumed to continue in 1980. Some DOE programs cannot be identified at the contractor level, and some elements of programs cannot be identified by states. These are listed in an Undesignated category. FY 1979 estimates are given; it is felt that Congressional actions on the FY 1980 budgets may affect the estimates shown.

To measure and classify the Post-Rosenbluth convective loss-cone instability in MFTF, we propose to use a CO/sub 2/ laser consisting of a TEA-pulsed section and a low pressure CW section, together with a light mixing receiver. Calculations show that this system offers sufficient power and sensitivity to detect instability throughout the range from strong coherent light scattering to weak incoherent scattering when the instability is eliminated.

A rapid and reliable method for analyzing technetium-99 in a wide variety of environmental samples, including waters, soils, stream sediments, and vegetations, has been developed. The procedure entails oxidizing the technitium to the heptavalent state and dissolving it in 6 N sulfuric acid. From that medium the technetium is quantitatively and selectively extracted into tributyl phosphate. A portion of the extract is then added to a scintillation cocktail, and technetium-99 activity is measured by liquid scintillation counting. Since a relatively large sample can be handled, the method can detest as little as 0.016 pCI /sup 99/Tc/ml water, 0.1 pCi /sup 99/Tc/g soil or sediment, and 0.2 pCi /sup 99/Tc/g vegetation. The procedure has also been adapted to analyzing urine samples, in which technetium activity as low as 0.12 pCi/ml can be detected.