Separate abstracts were prepared for each of the six included sections. (MOW)

The objective of the AAG pilot plant operation is to provide process data for the gasification and related sections of the demonstration plant. Since the pilot plant will not operate at the actual pressure of the demonstration plant, it is planned to perform tests at two different pressures to obtain a sound basis for pressure scale-up. Other objectives are listed briefly.

The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal divertor. The blanket concept selected by PPPL consists of a neutron multiplying converter region, containing natural Uranium Molybdenum (U-Mo) slugs followed by a fuel burning blanket region of molten salt containing PuF/sub 3/. PNL analyzed this concept to determine its structural, thermal and hydraulic performance characteristics. An adequate first wall cooling method was determined, utilizing low pressure water in a double wall design. A conceptual layout of the converter region tubes was performed, providing adequate helium cooling and the desired movement of U-Mo slugs. A thermal hydraulic analysis of the power-producing blanket regions indicated that either more helium coolant tubes are needed or the salt must be circulated to obtain adequate heat removal capability.

The first model of a modified Bond goniometer has been built and tested for the precision measurement of interplanar spacings in Si-single crystals. A change in interplanar spacing ..delta..d/d approximately = to +- 10/sup -5/ can be detected which corresponds to surface stresses of the order of +- 1000 psi. A second version of the goniometer is being assembled incorporating a removable microscope for precision alignment of the Si-strip into the primary X-ray beam.

A non-linear, time dependent, hydromagnetic model is developed and applied to the tearing mode, one of a class of instabilities which can occur in a magnetically confined plasma when the constraint of infinite conductivity is relaxed. The model is based on the eight partial differential equations of resistive magnetohydrodynamics (MHD). The equations are expressed as a set of conservation laws which conserves magnetic flux, momentum, mass, and total energy. These equations are then written in general, orthogonal, curvilinear coordinates in two space dimensions, so that the model can readily be applied to a variety of geometries. No assumption about the ordering of terms is made. The resulting equations are then solved by the method of finite differences on an Eulerian mesh. The model is applied to several geometries.

This report describes methods which can be used to limit the voltage across the generator for normal operation and various ground faults. It also contains quantitative information, obtained from the computer study, which can be used for evaluating the protection methods cost-wise.

A block of Pittsburgh seam bituminous coal and a block of Wyodak subbituminous coal were pyrolyzed under reducing gas in support of in situ gasification. Information from previously completed block pyrolysis of bituminous coal under an argon atmosphere show that differences in evolved gas result from differences in heating rates. Compared to block pyrolysis at 0.3 C/sup 0//min, block pyrolysis at 3 C/sup 0//min produces less gas but gas with a higher heating value, yielding a higher overall pyrolysis gas efficiency in recovering coal heating value. Experimental work on the fracture toughness and tensile properties of steels that may be used for piping and pressure vessels in very large gasification systems continued. The toughness of quenched 2/sup 1///sub 4/ Cr-1 Mo steel simulating the surface of a 254 to 305 mm-thick plate was measured, and the differences in toughness and tensile properties following two temperature treatments were determined. Post-weld heat treatment effects were also characterized. All properties remained within the range for ASME SA 387, Grade 22, Class 2 material. Work on inspection techniques for ceramic and cermet coatings is being closed out by completing and updating reports in various draft stages. Work is underway to establish a program for …

Small, surficial, secondary uranium deposits are present in several formations in the Sierra Nacimiento-Jemez Mountains region, but none of significant size are known. Field surveys indicate that the deposits are laterally discontinuous and are, in most cases, associated with carbonaceous debris. Mineral contents of as much as 0.18 percent U/sub 3/O/sub 8/ are recorded. There are 2 known deposits in the Pennsylvanian Madera Limestone, 18 in the Permian Cutler Formation, and 3 in the Triassic Chinle Formation. The Madera Limestone consists of a lower and an upper member. The lower member is predominantly a dense limestone and is lithologically unfavorable. The upper member, which consists of several arkosic units interbedded with cherty limestone, is not a favorable host rock because of its thin arkosic units, the paucity of carbonaceous debris, and its lithologically unfavorable limestone. The Cutler Formation consists mostly of interfingering siltstones and fine- to coarse-grained feldspathic and arkosic sandstones of fluvial origin. The sandstones are generally lenticular, average about 40 ft in thickness, and are favorable. Cutler equivalents south of lat 36/sup 0/ N. (Abo and Yeso Formations) were not included in this study. The Chinle Formation in the project area consists of five members. The Agua Zarca …

A newly developed test environment based on NaCl, Na/sub 2/SO/sub 4/, and HCl has provided some insight to several aspects of SCC in a transformable austenitic stainless steel. Current vs. time curves indicated the presence of the formation of a ''protective'' film which drastically reduced the anodic current leading to failure. This film, not indicated by the polarization curves, is subject to highly localized damage such as pitting. Thus, although it allows only very small corrosion currents, it is not truly protective. Hence, it is pseudo-passive. The critical cracking potential did not exhibit any difference between the annealed and the maximum (25%) deformation examined. The corrosion or open circuit potential for both annealed and deformed material behaved in a similar manner, becoming more noble with time until it reached the critical cracking potential and SCC ensured. The failure time for the deformed specimens was substantially shorter than for the annealed ones, but the incubation time was essentially the same. Within the range of experimental conditions examined thus far, it appears that the critical parameters leading to SCC in a chloride environment are primarily dependent on surface-environment interactions and not dependent on the bulk properties.

The production of D/sup -/ by multiple charge-transfer collisions of a D/sup +/ beam in a cesium-vapor target is considered for D/sup +/ energies above 300 eV. The cross sections relevant to D/sup -/ formation are obtained by a least-squares fit of three-charge-state differential equations to experimental yield curves. Implications for production of intense negative-ion beams are discussed, and speculations are made about extrapolation to lower engeries.

The Loss-of-Fluid Test (LOFT) facility is a highly instrumented, pressurized water reactor test system designed to be representative of large pressurized water reactors (LPWRs) for the simulation of loss-of-coolant accidents (LOCAs). Detailed structural analysis and appropriate instrumentation (accelerometers and strain gages) on the LOFT system provided information for evaluation of the structural response of the LOFT facility for loss-of-coolant experiment (LOCE) induced loads. In general, the response of the system during subcooled blowdown was small with typical structural accelerations below 2.0 G's and dynamic strains less than 150 x 10/sup -/6 m/m. The accelerations measured at the steam generator and simulated steam generator flange exceeded LOCE design values; however, integration of the accelerometer data at these locations yielded displacements which were less than one half of the design values associated with a safe shutdown earthquake (SSE), which assures structural integrity for LOCE loads. The existing measurement system was adequate for evaluation of the LOFT system response during the LOCEs. The conditions affecting blowdown loads during nuclear LOCEs will be nearly the same as those experienced during the nonnuclear LOCEs, and the characteristics of the structural response data in both types of experiments are expected to be the same. The LOFT …

A summation of information is presented on geology and drilling activity in the four primary study areas of the Western Gas Sands Project. The areas of interest are the Greater Green River Basin, the Piceance Basin, the Uinta Basin, and the Northern Great Plains Province. Drilling activity is discussed for the months of October, November, and December, 1977, with the major emphasis on wells located in low permeability sandstone areas, having significant gas production and utilizing hydraulic fracturing treatments. The drilling information was obtained primarily from ''The Rocky Mountain Region Report'' published by Petroleum Information Corporation on a daily basis. Another source of information was the ''Montana Oil and Gas Journal'' which is released weekly.

The sensitivity of primary knock-on atom (PKA) spectra and displacement per atom (DPA) cross sections to different secondary neutron energy and angular distributions and ''in-group'' weighting schemes is investigated. It is shown that the sensitivity of the PKA spectra and DPA cross sections for the (n,n' unresolved) and (n,2n) reactions in Fe to different angular distributions and the same secondary neutron spectrum is reasonably large (approximately 15%), whereas the sensitivity of these quantities to grossly different secondary neutron spectra and the same angular distribution is unexpectedly small. It is also shown that for Al the sensitivity of damage energy cross sections to different ''in-group'' weighting schemes is, for the most part, small.

The Model Number ORC1A3A01 System Accumulator for the Kilowatt Isotope Power System was expulsion tested and demonstrated to be in compliance with the requirements of Sundstrand Explusion Test Procedure, TP 400. Test requirements of TP 400 were extracted from the Kilowatt Isotope Power System, Ground Demonstration System Test Plan.

The mechanism of neutron induced current pulse generation in fission chambers is discussed. By application of the calculated detector transfer function to proposed detector current pulse shapes, and by comparison with actually observed detector output voltage pulses, a credible, semi-empirical, trapezoidal pulse shape of chamber current is obtained.

This report presents the analysis of the LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step thermal transient. Previous analysis performed under subcontract by Basic Technology Incorporated was utilized where applicable. The SAASIII finite element computer program was used to determine stress distributions in the nozzles due to the step transient. Computer results were then incorporated in the necessary additional calculations to ascertain that stress limitations were not exceeded. The results of the analysis indicate that both the spray and surge nozzles will be within stress allowables prescribed by subsubarticle NB-3220 of the 1974 edition of the ASME Boiler and Pressure Vessel Code when subjected to currently known design, normal operating, upset, emergency, and faulted condition loads.

A study was made of various factors that affect the visual inspection of thin film networks. The effect of various types of reflected illumination, the effect of defect size or shape, the time required for inspection, and the inspection uniformity were evaluated. The use of polarized light is recommended for the visual inspection of thin film networks.

The electrical resistivity and thermal conductivity of three high purity tantalum samples have been measured as functions of temperature over a temperature range of 5K to 65K. Sample purities ranged up to a resistivity ratio of 1714. The highest purity sample had a residual resistivity of .76 x 10/sup -10/OMEGA-m. The intrinsic resistivity varied as T/sup 3/./sup 9/ from 10K to 31K. The thermal conductivity of the purest sample had a maximum of 840 W/mK at 9.8K. The intrinsic thermal resistivity varied as T/sup 2/./sup 4/ from 10K to 35K. At low temperatures electrons were scattered primarily by impurities and by phonons with both interband and intraband transitions observed. The electrical and thermal resistivity is departed from Matthiessen's rule at low temperatures.

Factors that determined the data contents of the manual are presented. Estimates of errors in the data are provided, and the impact of these errors on solar design is discussed. The state is divided into 15 solar zones of roughly similar solar radiation conditions, which are illustrated along with page references to the most relevant solar and climate data. A guide to the data tables and graphs is provided, which are displayed under solar, climate, and sky charts. A guide is given to simplified design methods to predict performance and cost of solar heating and cooling systems. (MHR)

A major problem which arose during the reporting period was that of the completion of the required environmental analysis in order not to impact Phase II of the program. This problem was addressed and a proposed solution was agreed to. A sole source procurement justification for Energy Impact Associates was prepared and submitted to DOE for approval. This sole source procurement will enable construction start as scheduled (8 months after start of Phase II) whereas a competitive procurement of this item would have delayed that start by 6 months and with an additional inflationary cost to the program in excess of $5,000,000. The design work on the Commercial Plant is proceeding essentially on schedule. No major problems are foreseen. A major problem to be faced in 1978 is the achievement of successful operating data from the pilot plant necessary to confirm a demonstration plant design. This data must be obtained at a pressure of 3 atmospheres and requires additional modifications to the existing plant as described in IGT's Interface Plan submitted in January.

A system of four dipole magnets to be used for 180/sup 0/ electron scattering studies at the 400 MeV William F. Bates Electron Linear Accelerator of Middleton, Massachusetts was constructed and tested. The first three magnets through which the incident beam passes have similar pole shapes and serve only as beam transport elements. The fourth magnet directs the incident beam onto a target, and also receives and deflects the backscattered electrons into a large magnetic spectrometer operating in an energy-loss mode. The system may be used for both elastic and inelastic electron scattering without moving the spectrometer. The incident beam and the post-target beam travel along the same line. Tests show that a constant solid angle is maintained for scattering regardless of the energy loss suffered by the electron in the target. A resolution inherent to the system of less than 2.5 x 10/sup -4/ was found.

Mixtures of H/sub 2/--T/sub 2/ or D/sub 2/--T/sub 2/ will exchange to produce HT or DT due to catalysis by the tritium ..beta.. particle. The kinetics of the reaction D/sub 2/ + T/sub 2/ = 2DT may play an important role in designing liquid or solid targets of D/sub 2/--DT--T/sub 2/ for implosion fusion, and distillation schemes for tritium cleanup systems in fusion reactors. Accordingly, we have critically reviewed the literature for information on the kinetics and mechanism of radiation-induced self-exchange reactions among the hydrogens. We found data for the reaction H/sub 2/ + T/sub 2/ = 2HT in the gas phase and developed a scheme based on these data to predict the halftime to equilibrium for any gaseous H/sub 2/ + T/sub 2/ mixture at ambient temperature with an accuracy of +-10 percent. The overall order of the H/sub 2/ + T/sub 2/ = 2HT reaction is 1.6 based on an initial rate treatment of the data. The most probable mechanism for radiation-induced self-exchange reaction is an ion-molecule chain mechanism.

The details of a shingle module design which produces in excess of 97 watts/m/sup 2/ of module area at 1 kW/m/sup 2/ insolation and at 60/sup 0/C are reported. This selected design employs a tempered glass coverplate to provide the primary solar cell structural support. The use of the B.F. Goodrich FLEXSEAL roofing system as the outer skin of the shingle substrate provides a high confidence of achieving the 15 year service life goal. The fabrication and testing of a preproduction module of this design has demonstrated that this selected approach will meet the environmental testing requirements imposed by the contract. Attempts to fabricate a preproduction module of an alternative design, which embeds the solar cell assembly within a methyl methacrylate casting, proved unsuccessful.

One method being considered for interim storage of high-level radioactive waste materials is to place these materials in large sealed stainless steel canisters and subsequently store these canisters in a second sealed steel storage cask. Weld procedures are proposed as the closure or seal for these vessels. Inspection of these closures to assure initial and long-term integrity of the closure welds presents a challenge to nondestructive testing. The environment is thermally (400 to 1000/sup 0/F) and radioactively (10/sup 5/ R/hr) hot necessitating remote inspection procedures. As a result of research work, ultrasonic test techniques were developed for inspecting the final weld closure of the waste cask. Special transducers, coupling techniques and fixturing were developed and demonstrated in a mockup test facility by remotely examining a 2-in. full penetration weld closure. The examination was performed at room ambient and at a temperature of 200/sup 0/F. Testing at the desired temperature of 400/sup 0/F was not completed due to a loss in transducer performance at temperatures in excess of 200/sup 0/F. Upon completion of the mockup test demonstration, the cask was subjected to a drop test. The ultrasonic results of the pre- and post-examination of two weld closures (the 2-in. full penetration …