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 splitting of interstitial loops formed by irradiation is considered in detail. It is shown that they may split to form obtuse--angled single shear faults on the intersecting (111) planes. A detailed description of the splitting is given in which the interstitial Frank loop is viewed as being made up of perfect dislocation loop and two shears. The detailed description is then considered in the context of the formation of complex loops as are observed in quenching and irradiation studies. Experimentally observed geometries are explained viz, triangular loops within hexagonal ones etc. The nucleation of a DC' loop in complex interstitial loop formation is shown to be feasible. DC' has the magnitude of a perfect dislocation loop and encloses an intrinsic shear. (auth)

This quarterly report is the fourth 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. The work reported here was performed during the period January through March 1977.

Construction of the Shiva laser system is nearing completion. This laser will be operating in fall 1977 and will produce over 20 terawatts of focusable power in a subnanosecond pulse. Fusion experiments will begin early in 1978. It is anticipated that thermonuclear energy release equal to one percent that of the incident light energy will be achieved with sub-millimeter deuterium-tritium targets. From other experiments densities in excess of a thousand times that of liquid are also expected.

It was shown that by the use of ion beam probing system with the proper detectors experimental expressions can be obtained for v/sub o/ = v/sub o/ (x,y,z) and v/sub d/ = v/sub d (x,y,z). It was also shown that by taking the curl of the difference between the equations, the magnetic field and consequently the plasma current density distribution can be evaluated.

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 corrosion of several iron- and nickel-base alloys in supercritical steam at 24.1 MPa (3500 psi) and 538/sup 0/C was measured to 7.92 x 10/sup 7/ s (22,000 h). The experiments were carried out in TVA's Bull Run Steam Plant. Corrosion was measured almost entirely by weight change and visual appearance; a few samples were evaluated by more descriptive analytical techniques. The corrosion rates of low-alloy ferritic steels containing from 1.1 to 8.7 percent Cr and 0.5 to 1.0 percent Mo differed by less than a factor of 2 in steam. Several modified compositions of Hastelloy N were evaluated and found to corrode at about equivalent rates. Of the alloys studied, the lowest weight gain in 3.6 x 10/sup 7/ sec (10,000 hr) was 0.01 mg/cm/sup 2/ for Inconel 718 and the highest 10 mg/cm/sup 2/ for the low-alloy ferritic steels. 25 figures, 3 tables.

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.

The DT fusion neutron irradiation of two LLL superconductor wires at 4.2/sup 0/K is described. The sample position, beam-on time, and neutron dose record are given. The results from four ''profile'' dosimetry foils measuring the lateral variation in neutron flux are included.

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)

Conditions are discussed under which an interface, possibly containing an adsorbed species, is capable of sustaining an atomistically sharp cleavage crack, rather than having any such crack blunt out via dislocation nucleation. Two models for ductile versus brittle interface response are discussed. One of these is applied to model grain boundaries in face centered cubic materials, and is used to compare predictions with experimental observations on the embrittlement of Cu polycrystals by the addition of dilute concentrations of Bi. The general results are in qualitative agreement, although the model predicts behavior that is, in general, more ductile than that observed experimentally. Several possible reasons for this excess ductility are discussed. An appendix presents an analysis of the work of reversible separation of an interface containing a segregated species. This is intended to clarify some issues recently raised in the literature on interfacial embrittlement, especially concerning the distinctions that must be drawn between expressions for cohesive energy reductions for interfacial separation at constant chemical potential, ..mu.., versus separation with constant concentration, GAMMA, of the adsorbate species.

In tokamak plasmas subjected to substantial toroidal-field ripple, sufficiently energetic members of the bulk-iron population can diffuse rapidly away from the hot central region by the superbanana process. The result is a truncation of the ion velocity distribution, causing a marked reduction in the fusion reactivity. This tail-depletion effect may account in part for the anomalously low central ion temperature deduced from the neutron flux emitted from dense deuterium plasmas in the Alcator device, and also may have relevance to similar observations in the beam-heated TFR plasma.

The goal of the ERDA/JPL LSSA program of $0.50/W selling price for array modules in 1986 turns out to have been remarkably appropriate. An extensive and detailed analysis of technologies which could be related to array module manufacturing was completed and a minimum manufacturing cost in a highly automated line of $0.30/W was found assuming the silicon is free. The panels are of a double glass construction and are based on round wafers. Screen printed silver has been used as the metallization with a spray-coated AR layer. The least expensive junction formation technology appears to be ion implantation; however, several other technologies also may be used with very little cost penalty as described. Based on the required investment, a profit of $0.05/W appears reasonable. If silicon wafers are available at a price of $20 to 40/M/sup 2/, a selling price for these array modules of $0.50 to 0.66/W is projected. An analysis of the impact of factory size has been made. For a production level of 500 MW/yr, the price above is derived. For comparison, a factory processing 50 MW/yr using the same technology would sell modules for $0.54/W to $0.70/W. An analysis of the impact of wafer size indicates …

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.

A computer routine, the Transmissivity Iterative Routine (TIR), has been developed for calculating the hydraulic conductivity distribution in highly heterogeneous aquifers where characterization by field measurement methods alone would be prohibitive in cost. The routine yields the two-dimensional distribution of hydraulic conductivity averaged over the aquifer thickness. The agreement between the calculated and actual average conductivity is dependent on the degree to which the groundwater system satisfies the Dupuit assumption. The program was written for an interactive computer system with a light-pen, CRT display and graphical digitizer, which allow rapid reinterpretation and evaluation of groundwater contours. Testing of the computer program on a synthetic surface identified a set of control parameters that resulted in a maximum computational error of +-5 percent. This maximum error occurred as streamtubes passed near stagnation points where the groundwater hydraulic potential gradients and radii of curvature were small. Sensitivity tests on the Hanford unconfined aquifer indicated that the hydraulic conductivity calculation is not particularly sensitive to errors in the storage coefficient distribution over much of the aquifer. These tests also illustrated the power of the TIR method to evaluate the validity of field data.

The projects reported each quarter are the following: Gas Reactor Safety Evaluation, THOR Code Development, SSC Code Development, LMFBR and LWR Safety Experiments, Fast Reactor Safety Code Validation, Technical Coordination of Structural Integrity, and Fast Reactor Safety Reliability Assessment.

This report is intended as a ''quick-look'' report summarizing the experimental results obtained from pressure suppression experiment numbers 2.1, 2.2, and 2.3 that were performed on the Lawrence Livermore Laboratory's 1/5-scale boiling water reactor (BWR) Mark I pressure suppression experimental facility on April 26, 1977. A brief description of the general nature of the tests and a summary of the actual tests that were performed are given.

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.

Four different techniques for sample preparation were evaluated for determining vanadium and nickel in crude oils by atomic absorption (AA) spectroscopy: (1) The flame-analyzed dilution method which consists of direct-flame AA analysis after diluting the sample with a suitable organic solvent; (2) the flame-analyzed, wet-ashing method in which the sample is combusted and the residue is then dissolved before flame analysis; (3) the flameless, dilution method which involves flameless AA analysis of the sample following dilution with a suitable organic solvent; and (4) the direct, flameless method in which the crude oil or residue is directly analyzed by flameless AA. The flame-analyzed dilution method yielded erratic and inaccurate analytical results for samples of crude oils as well as for a residual sample containing standard amounts of vanadium and nickel; hence, it is unsatisfactory for oil-identification. Similarly, the direct, flameless method is unsatisfactory owing to the small concentration range available for analysis (less than approximately 15 ppM). Both the flame-analyzed, wet-ashing and flameless-dilution methods yield reliable and reproducible (better than 10%) quantitative data for nickel and vanadium in crude oils and crude oil residues. Results demonstrate that the error associated with the loss of volatile metal containing compounds upon wet-ashing is …

The predicted output energy of the Sandia Atomic Iodine Laser SAIL-1 is given for various numbers of preamplifier stages and for various small signal gains in each stage. Additional possibilities for further increasing the output energy are given.

The suggestion of S. van der Meer for stochastic cooling or feedback damping of a circulating charged particle beam offers promise of increasing the luminosity of a storage ring and may be a particularly attractive technique if antiprotons are to be employed as one of the beams in such a device. The original report of van der Meer considered the repeated use of a kicker to suppress the transverse phase-space displacement of the centroid of a group of particles detected at a pick-up station situated up-stream, and the report estimated the expected rate of damping of the mean-square oscillation amplitude. This analysis is extended so as to provide information on the manner in which the character of the amplitude distribution function may be affected by the damping procedure mentioned above. It is believed that information concerning the evolution of the form of the distribution function may be of particular interest in cases in which a ''halo'' is imposed on the distribution by injection of a group of particles to supplement those in a beam that has already been subjected to appreciable feedback damping. Results of the analytic work is illustrated, and compared with the results of simulation computations.