The use of ultrasonic methods in nondestructive testing depends on the interpretation of the scattering of sound waves by flaws. The theory of elastic waves and their scattering in non-uniform media is developed in detail from first principles, and in generality. Both integral equation and differential methods are discussed, with emphasis on the former. General methods for defining scattering cross sections are presented, and conservation theorems are noted. The Born Approximation to the integral equation is presented, and computed results for several experimental situations are discussed. Several corrections to papers in the literature are made, and in particular the exact scattering of a transverse wave by a spherical flaw is compared with the Rayleigh (long wave) limit.

A high temperature amplifier for use in geothermal well logging was developed. This development was based on the use of ceramic vacuum tubes as the active circuit element, since these tubes have the capability to operate in the high ambient temperature environment. The primary goal of this program was to design, build, and deliver a prototype amplifier capable of continuous operation in a 250/sup 0/C environment. A development program designed to meet this goal covered four phases. These phases were (1) development of the basic circuit configuration with conventional, low cost glass envelope vacuum tubes; (2) modification of the circuitry to accommodate the ceramic vacuum tubes; (3) a 1000-hour duration temperature cycle (48 hours at 260/sup 0/C and 2 hours at 20/sup 0/C); and (4) development of a prototype, deliverable amplifier. The following sections discuss the high temperature amplifier development program. Section 2 describes the amplifier performance, including design requirements, circuit design, development program, and the prototype amplifier. Section 3 presents test results from two breadboard models, one with conventional glass tubes and one with ceramic tubes, and the prototype amplifier. Section 4 describes the operation of the prototype amplifier. Circuit equations used for analysis and tube characteristics are contained …

The authors report here on latest results from an investigation of the form of the neutral current coupling in the inclusive channels {nu}{sub {mu}} + N {yields} {nu}{sub {mu}} + hadrons and {bar {nu}}{sub {mu}} + N {yields} {bar {nu}}{sub {mu}} + hadrons. The experiment was conducted by the Caltech-Fermilab group in October 1974. The data were taken in the Fermilab narrow band beam set to a mean secondary hadron energy of {+-} 170 GeV. The distributions of total energy, observed in the target calorimeter, for charged current events in which the muon momentum was measured, shown in figure 1, reflect the dichromatic structure of the beam, with average energies for neutrinos from pion and kaon decay of 50 and 150 GeV, respectively. The two main sources of background present in the data sample come from cosmic ray interactions. and from neutrinos (and anti-neutrinos) which are produced by decays before momentum and sign selection has occurred (wide-band background). Both backgrounds are measured and empirically subtracted from the data. The first (cosmic rays) is measured in an off-beam gate. The second (wide-band) is measured by closing a slit at the entrance to the decay pipe. Thus, the data sample contains beam …

An extensive literature search was made to locate technical publications and computer programs relating to wellbore temperatures during drilling operations. Publications obtained are listed in the References. Two approaches were used in calculating borehole temperatures: The steady state solution of Holmes and Swift was programmed and 2100 cases calculated for various borehole configurations. For transient temperature studies, Exxon Production Research Co. made calculations for ten borehole configurations under subcontract. These calculations emphasize the need for better high temperature bit performance and improved engineering procedures in drilling.

An experimental program was conducted to determine the operating characteristics of full length (65 feet) single and multi-tube once-through steam generator test sections subjected to radiant heat flux levels commensurate with commercial solar tower receiver application. Absorbed heat flux levels ranging from 0.15 to 0.71 Btu/in./sup 2/-sec (0.25 to 1.16 MW/m/sup 2/) were achieved in a horizontal facility utilizing graphite radiant heater arrays. Steam exit temperatures ranged from 625 F (two-phase) to 1380 F at pressures of 1000 to 2300 psia. Wall temperature profiles and fluid pressure losses were obtained and compared with an existing computer model.

Perhaps the most important design consideration is the heat generated by the spent fuel assemblies or the high-level waste being placed in the repository. The sensitivity of repository design to this heat is reflected by the definition of temperature and thermochemical criteria. To assure environmental and occupational safety, limits may be placed on such parameters as spent fuel or waste temperature, canister temperature, rock temperature, strength-to-stress ratio of the excavated openings, surface uplift or subsidence, temperature increase in an aquifer, and temperature increase at or near the surface of the earth. Appropriate criteria are chosen to accomplish ready retrievability, to retard canister corrosion, to suppress the rate of nuclide leaching, to control the buoyant forces that drive potential nuclide migration, to assure mine safety, to assure formation stability, and to control the thermal and thermomechanical impact on the environment. Other major concerns in the location and design of a waste repository are the presence and effect of groundwater within the repository host rock and the surrounding strata. Additional groundwater considerations include its effect on canister integrity, its potential as a source of hydrogen, and its effect on the repository operational environment. Two types of retrieval are considered: operational verification and …

This report presents a physical description of a reference deep-geologic repository located in a granite host rock at a depth of about 1500 meters. Two reference repository designs are described in this report. One is designed to accept wastes from a lightwater reactor (LWR) strategy in which no reprocessing occurs, and the spent fuel itself is considered a waste form. The second is designed to accept wastes from an LWR strategy with reprocessing in which uranium and plutonium are recycled.

Progress is reported on the following: well conditions; perforating and cementing; temperature-depth plot; slotted liner, well head and auxiliary equipment; well testing and analysis program; well monitoring during standby; environmental assessment; time schedule; and budgets. (MHR)

A thermal analysis was performed to establish requirements for a heating system for the standpipe bubbler sufficient to maintain the sodium in the standpipe in a liquid condition over the range of operating conditions. There are very few formal requirements on operating limits or hardware selection. Therefore, consideration was given to standard types of equipment employed in a conventional manner. The recommended heating system consists of metal-sheathed resistance heaters with three units being mounted on standoffs and equally spaced around the pipe. The heaters would be covered by a layer of insulation having both interior and exterior coverings of reflective metal sheathing. The pipe temperature would be monitored by thermocouples, and the heaters would be turned on and off on a cycle of approximately 4 hours to maintain the pipe at a temperature of 800/sup 0/F +- 50/sup 0/F.

None

The behavior of dielectric droplets and gas bubbles in electrostatic levitation, positioning, and control devices for laser-fusion target applications is studied. Because of the exacting tolerance requirements for the sphericity of laser fusion targets, there is concern over the electric field induced elongation effect which may exist in some or all of these schemes. These proposed tolerances suggest upper limits on the axis ratio ..gamma..: ..gamma.. - 1 < 10/sup -3/, which may severely limit the maximum allowable electric field in certain electrostatic levitation schemes. Calculations of the deformation of bubbles in cryogenic hydrogen were undertaken by Bliss, but only for large deformations up to ..gamma.. approximately 2. These calculations are extended down to very small deformations, that is: 10/sup -4/ < ..gamma.. - 1 < 10/sup -1/, for droplets of cryogenic liquid hydrogen (n - H/sub 2/) and bubbles in liquid hydrogen at its triple point. Also, the effect of pressure on the deformation has been explored. Further, approximate explicit analytic expressions for ..gamma..(E) have been obtained for the limit of small deformations.

The feasibility of photochemically fractionating the actinides in nuclear waste processing has been evaluated on a preliminary basis. The data indicate that there are potentially useful photo-redox reactions. However, there is a serious lack of data on photochemical parameters for the solutions conditions which exist in nuclear waste processing. The problem areas relevant to photochemical processing are identified. The experimental areas which must be investigated in order to further evaluate the photochemistry are defined. A research and development program is required to determine whether these photochemical reactions can be successfully modified and adapted into a functional actinide fractionating process.

General requirements for the Brayton Isotope Power System (BIPS)/Ground Demonstration System (GDS) assembly and test facility are defined. The facility will include provisions for a complete test laboratory for GDS checkout, performance, and endurance testing, and a contamination-controlled area for assembly, fabrication, storage, and storage preparation of GDS components. Specifications, schedules, and drawings are included.

The design and fabrication of a test mask suitable for the experimental evaluation of automated integrated circuit photomask inspection systems is described. This mask contains various types and sizes of intentional defects in known locations. The defects are superimposed on a background of images consisting of a typical integrated circuit pattern.

The stability of dissipative trapped-particle modes in the presence of a self-consistent lower-hybrid pump is analyzed theoretically. The pump can either be a single coherent wave or a spectrum of turbulent waves. Corresponding dispersion relations modified by the pump are derived and conditions for excitation and suppression of the modes are also discussed.

The report is a synoptic review of data collected over the past twenty years on the chemistry of Lake Michigan. Changes in water quality and sediment chemistry, attributable to cultural and natural influences, are considered in relation to interacting processes and factors controlling the distribution and concentration of chemical substances within the Lake. Temperature, light, and mixing processes are among the important natural influences that affect nutrient cycling, dispersal of pollutants, and fate of materials entering the Lake. Characterization of inshore-offshore and longitudinal differences in chemical concentrations and sediment chemistry for the main body of the Lake is supplemented by discussion of specific areas such as Green Bay and Grand Traverse Bay. Residues, specific conductance, dissolved oxygen, major and trace nutrients, and contaminants are described in the following context: biological essentiality and/or toxicity, sources to the Lake, concentrations in the water column and sediments, chemical forms, seasonal variations and variation with depth. A summary of existing water quality standards, statutes, and criteria applicable to Lake Michigan is appended.

The cyclotron resonance of the piezoelectric polaron in n-CdS has been investigated using far infrared spectroscopy at magnetic fields to 90 kOe. Both lamellar grating and Michelson Fourier transform spectrometers were used with a 0.3/sup 0/K Ge bolometer to study the photon energy region from 10 cm/sup -1/ to 60 cm/sup -1/. The theory of Miyake predicts that the frequency of the polaron's cyclotron resonance is shifted from the bare hand electron resonance frequency according to the expression: ..delta omega../sup p//sub c// ..cap omega../sub c/ varies as H/sup -1/ T/sup /sup 2///sup 3//. The magnetic field dependence of the present cyclotron resonance confirms this expression; the cyclotron mass isiezoelectric polaron effects. The bare band mass in n-CdS has also been determined by taking into account the Froehlich polaron interaction in addition to the piezoelectric polaron effects. For H parallel to the c-axis this cyclotron mass is 0.155 +- 0.005 m. The polaron pinning due to the 43 cm/sup -1/ optically inactive phonon has been observed.

Leachabilities of cesium and strontium from the glass matrices were correlated with the microstructures of glasses containing waste sludge from two SRP waste tanks. All sludge components, except mercury which volatilized, were completely soluble in the melt, but small amounts of crystalline iron oxide precipitated during cooling. These precipitates were less leachable than the glass matrix. Even though the compositions of the two sludges that were tested were similar, glass containing one of the sludges devitrified during heating at 600/sup 0/C; glass containing the other sludge did not devitrify. Leachability of the devitrified glass was as much as 100 times greater than that of nondevitrified glass, but still very low, less than 10/sup -6/ g/(cm/sup 2/)(day).

Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes. (JGB)

Work was carried out on the following: HTGR reprocessing development and pilot plant, refabrication development and pilot plant, recycle fuel irradiations, engineering and economic studies, and conceptual design of a commercial recycle plant. (DLC)

A description is given of the development and verification of a generalized coupled conduction-convection, multichannel heat transfer computer program to analyze specific safety questions involving high temperature gas-cooled reactors (HTGR). The HEXEREI code was designed to provide steady-state and transient heat transfer analysis of the HTGR active core using a basic hexagonal mesh and multichannel coolant flow. In addition, the core auxiliary cooling systems were included in the code to provide more complete analysis of the reactor system during accidents involving reactor trip and cooling down on the auxiliary systems. Included are brief descriptions of the components of the HEXEREI code and sample HEXEREI analyses compared with analytical solutions and other heat transfer codes.

Transport processes in large measure determine the rate at which electrolytic metal deposition and dissolution can be conducted. Unusually high rates, often accompanied by the formation of solid reaction products, are achieved in electrochemical machining by the use of high electrolyte flow velocities between closely-spaced electrodes. Geometrical shape and surface finish resulting from deposition or dissolution reactions are determined by the current distribution on a macroscopic and microscopic scale. Macroscopic current distributions have been determined experimentally by different electrical and optical means and are compared to theoretical expectations based on transport correlations and numerical models.

The report describes the objectives and present status of a study concerning the operational reliability of nuclear power plants. The purpose of the study is to develop utilitarian models for use with the Liquid-Metal-Cooled Fast Breeder Reactor; initial testing of the formalism can be carried out with LWR operational data. Methods are being directed towards (1) day-to-day operation of the nuclear plant protection system and (2) to better understand the protection system sensor characteristics in order to anticipate off-normal conditions. The initial models now underway are based on moment-matching, confidence bounding, and convolution methods in the case of the protection system reliability, and for the sensor response function, a convolution of component reliability probability distributions and noise signatures.

Several approaches for characterizing the physical and aerodynamic properties of irregularly shaped aerosol particles are reviewed. Measurements of density modification factor, dynamic shape factor, and particle density using an aerosol centrifuge and a scanning electron microscope are described. Calibration procedures for this characterization method are described and preliminary results reported.