Geologic and geochemical criteria were developed for the occurrence of economic uranium deposits in alkaline igneous rocks. A literature search, a limited chemical analytical program, and visits to three prominent alkaline-rock localities (Ilimaussaq, Greenland; Pocos de Caldas, Brazil; and Powderhorn, Colorado) were made to establish criteria to determine if a site had some uranium resource potential. From the literature, four alkaline-intrusive occurrences of differing character were identified as type-localities for uranium mineralization, and the important aspects of these localities were described. These characteristics were used to categorize and evaluate U.S. occurrences. The literature search disclosed 69 U.S. sites, encompassing nepheline syenite, alkaline granite, and carbonatite. It was possible to compare two-thirds of these sites to the type localities. A ranking system identified ten of the sites as most likely to have uranium resource potential.

A description is presented of a general algorithm for locating the extremum of a multi-dimensional constrained function. The algorithm employs a series of techniques dominated by random shrinkage, steepest descent, and adaptive creeping. A discussion follows of the algorithm's application to a ''real world'' problem, namely the optimization of the price of electricity, P/sub eh/, from a hybrid fusion-fission reactor. Upon the basis of comparisons with other optimization schemes of a survey nature, the algorithm is concluded to yield a good approximation to the location of a function's optimum.

A one-dimensional (1-D), multifluid transport model is used to investigate the effects of particle fueling profiles on plasma transport in an ignition-sized tokamak (TNS). Normal diffusive properties of plasmas will likely maintain the density at the center of the discharge even if no active fueling is provided there. This significantly relaxes the requirements for fuel penetration. Not only is lower fuel penetration easier to achieve, but it may have the advantage of reducing or eliminating density gradient-driven trapped particle microinstabilities. Simulation of discrete pellet fueling indicates that relatively low velocity (approximately 10/sup 3/ m/sec) pellets may be sufficient to fuel a TNS-sized device (approximately 1.25-m minor radius), to produce a relatively broad, cool edge region of plasma which should reduce the potential for sputtering, and also to reduce the likelihood of trapped particle mode dominated transport. Low penetrating pellets containing up to 10 to 20 percent of the total plasma ions can produce fluctuations in density and temperature at the plasma edge, but the pressure profile and fusion alpha production remain almost constant.

The theoretical background for the finite element computer program, NACHOS, is presented in detail. The NACHOS code is designed for the two-dimensional analysis of viscous incompressible fluid flows, including the effects of heat transfer. A general description of the fluid/thermal boundary value problems treated by the program is described. The finite element method and the associated numerical methods used in the NACHOS code are also presented. Instructions for use of the program are documented in SAND77-1334.

A Hamilton Standard 7.5-kW electron-beam welder has been extensively rebuilt, upgraded, and computer automated to provide accurate, repeatable, multipass, wirefed welds with stored seam tracking. Tests have shown that the seam-tracking system can keep the beam on a true line within approximately +-0.05 millimeter, even in the presence of a strongly deflecting magnet.

The predictive value of short-term genetic tests, such as the Salmonella and Escherichia coli (K-12, 343/113) systems including microsomal activation, is well documented. We have applied the short-term testing to various crude products and effluents from the synthetic fuel technologies. Class fractionation and column chromatography of the test materials and the coupled bioassays can be used to identify the most active fractions (collaborative effort with Analytical Chemistry Division). Reversion at the histidine locus for Salmonella was assayed with each fraction and the results are expressed in units of revertants (strain TA98) per milligram of the starting material (organic content) including metabolic activation with a crude rat liver preparation. Results obtained with the Salmonella system were validated by employing E. coli strains auxotrophic for arginine. Genetic activity is seen with a variety of fractions, largely the basic and neutral (PAH) components. Total activity varies from process to process, thus, the short-term genetic test can be considered a useful prescreen for potential biohazard of various effluents both in plants and in the immediate plant environment.

This report contains the results of a validation test of the ANL Fish Impingement Model. By the use of 1974 fish-impingement and environmental data from the Zion Nuclear Power Station, it is shown that the modified and expanded mathematical model yields reasonably good results in calculations of daily fish-impingement losses at the cooling water intakes. Comparisons confirmed that the fish-impingement process depends primarily on the abundance of fish in the vicinity of a cooling water intake, whereas the probability function gives the susceptibility to impingement provided that fish are present in the intensity region. In view of the limited amount of information available with regard to the various environmental and fish-abundance factors, it appears that the present form of the model is adequate and that efforts to refine the model further are not warranted.

In recent years there has been extensive study of nuclear shape parameters by electron scattering, ..mu.. meson atomic transitions, Coulomb excitation and direct nuclear inelastic scattering. Inelastic scattering of strongly absorbed particles, e.g., alpha-particles and heavy ions, at energies below and above the Coulomb barrier probe the charge and mass distributions within the nucleus. This paper summarizes measurements in this field performed at Oak Ridge National Laboratory.

The objective of this document is to outline the test plan for the KIPS Technology Verification Program. This test plan is inclusive of component simulating (rig) testing, component testing and system testing. Rig testing will prove concept feasibility, measure basic performance and to develop the hardware necessary prior to initiation of GDS component part manufacture. Component testing will measure basic performance and verify component integrity prior to GDS assembly. The GDS system testing will: simulate the flight system operation; determine the life limiting components; measure performance and relate to potential system lifetime; demonstrate 18+% DC generating efficiency; and perform a 5000 h endurance test with final configuration hardware.

Experimental studies of thermally induced changes in a simulated nuclear waste glass were conducted to define the composition and concentration of all phases formed over a broad range of time (up to one year) and temperature (<1200/sup 0/C) conditions. Depending on time and temperature, a steady-state condition is achieved in which a number of crystalline phases coexist with a glass phase which is partially depleted of some elements. Concentrations of the phases increase with decreasing temperature but usually reach only a fraction of their maximum theoretical concentration. Considering the major phase formed (Zn/sub 2/SiO/sub 4/), this fractional concentration is about 10% at 900/sup 0/C and 45% at 700/sup 0/C, when equilibrium is achieved. Under these unfavorable time/temperature conditions, the glass is about one-third crystalline. Because of melt insolubles (RuO/sub 2/,Pd) the most homogeneous glass will contain approximately 3% crystalline phases. Crystallization occurs at rates in agreement with those estimated from theory, based on a knowledge of the glass viscosity and an estimated heat of crystallization for the Zn/sub 2/SiO/sub 4/ phase. The times to reach steady-state concentrations range from a few hours at 900/sup 0/C to approximately 1 year at 700/sup 0/C. No crystallization at 500/sup 0/C was observed after …

An electrostatic scanning system has been designed and built to uniformly implant a 1 cm/sup 2/ sample with a charged particle beam. The full angular scan capability for a 2 MeV beam is 0.5 degrees at 6 kV p-p. The design of the system is extremely simple so it is very compact, easy to operate, and has shown very good reliability.

The fission cross ratios of /sup 239/Pu to /sup 235/U were measured over the neutron energy range of 0.1 to 10 MeV. The atom ratios of the samples were based on their relative thermal fission rates and on their alpha activity.

Complete descriptions of the mathematical models and numerical methods used in the code LAPU2 are presented. This code can be used to study the propagation with diffraction of a temporally finite pulse through a sequence of resonant media and simple optical components. The treatment assumes cylindrical symmetry and allows nonlinear refractive indices. An unlimited number of different media can be distributed along the propagation path of the pulse. A complete users guide to input data is given as well as a FORTRAN listing of the code.

The radiological hazard resulting from an exposure to either tritium oxide or tritium gas is discussed and the factors contributing to the hazard are presented. From the discussion it appears that an exposure to tritium oxide vapor is 10/sup 4/ to 10/sup 5/ times more hazardous than exposure to tritium gas. Present and future sources of tritium are briefly considered and indicate that most of the tritium has been and is being released as tritium oxide. The likelihood of gaseous releases, however, is expected to increase in the future, calling to task the present general release assumption that 100% of all tritium released is as oxide. Accurate evaluation of the hazards from a gaseous release will require a knowledge of the conversion rate of tritium gas to tritium oxide. An experiment for determining the conversion rate of tritium gas to tritium oxide is presented along with some preliminary data. The conversion rates obtained for low initial concentrations (10/sup -4/ to 10/sup -1/ mCi/ml) indicate the conversion may proceed more rapidly than would be expected from an extrapolation of previous data taken at higher concentrations (10/sup -1/ to 10/sup 2/ mCi/ml).

This is the 17th monthly report on the Jolly Tiger (Albany, NY) Restaurant Project and presents tabulated data on: sales, energy consumption, water usage, heating and cooling requirements, and weather conditions. The data were acquired throughout April 1978. (LCL)

The increased incidence of thyroid nodularity and carcinoma appearing as a late effect after exposure of the human thyroid to ionizing radiation is well-recognized. Despite the high prevalence of thyroid nodularity in Marshallese inadvertently exposed to fallout in 1954, only two subjects, both about one year of age at exposure, have been found to have primary hypothyroidism. The recent availability of sophisticated immunoassay techniques for thyroxine (T/sub 4/) and thyrotropin (TSH) has allowed more thorough thyroid evaluation of the exposed population who do not have known thyroid abnormalities (43 Rongelap people). Four of 43 Rongelapese had abnormally high basal TSH and TRH-induced TSH release on two such tests as opposed to only 2 of 214 controls. Plasma T/sub 4/ concentrations were low, or low-normal in these individuals. These results indicate the presence of early thyroid dysfunction. Several other subjects have shown at least one abnormal finding but have not had the required number of tests to meet the established criteria. In /sup 3///sub 4/ of these subjects the estimated thyroid exposure dose was less than 400 rads. Hypothyroidism has been previously noted after therapeutic doses of /sup 131/I for hyperthyroidism, but not in individuals exposed to the relatively low levels …

The multigroup photon diffusion equations are derived from the Boltzmann equation. Limitations and assumptions imposed by the diffusion equation are thus apparent. In addition, this approach serves to define all of the required diffusion parameters in terms of cross sections; the relationship to the multi-band parameters used in neutron transport calculations can thus be clearly established. All required two-band parameters are defined in terms of Planckian and Rosseland mean values. (RWR)

The paper starts with a review of some currently available simplified inelastic analysis methods used in elevated temperature design for evaluating plastic and thermal creep strains. The primary purpose of the paper is to investigate how these simplified methods may be applied to fast breeder reactor core design where neutron irradiation effects are significant. One of the problems discussed is irradiation-induced creep and its effect on shakedown, ratcheting, and plastic cycling. Another problem is the development of swelling-induced stress which is an additional loading mechanism and must be taken into account. In this respect an expression for swelling-induced stress in the presence of irradiation creep is derived and a model for simplifying the stress analysis under these conditions is proposed. As an example, the effects of irradiation creep and swelling induced stress on the analysis of a thin walled tube under constant internal pressure and intermittent heat fluxes, simulating a fuel pin, is presented.

This report is a study of the feasibility of computerized automation of the Laboratory Services Branch of the Environmental Protection Agency's Region IV. The LSB provides chemical analytical support for a number of EPA divisions; its primary function at present is compliance monitoring, field surveys, and oil identification. Automation of the LSB is not only feasible but also highly desirable. Automation systems are proposed that will make major improvements in analytical capacity, quality control, sample management, and reporting capabilities. Most of these automation systems are similar to those already developed and installed at other EPA laboratories. These systems have options that include limited modifications suggested as a result of the study of the LSB Laboratory, and also include communications hardware and software for a Sample File Control host computer. It is estimated that the initial cost of three of the four options considered would be recouped in approximately three years through increased capacity and efficiency of operation.

Many detailed multigroup transport calculations require group-to-group Legendre transfer coefficients to represent scattering processes in various nuclides. These (fine-group) constants must first be generated from the basic data. An alternative technique for generating such data from the total scattering cross section of a particular nuclide on a pointwise energy basis, sigma(E'), and some information regarding the angular scattering distribution for each initial energy point is outlined. The evaluation of generalized multigroup transfer matrices for transport calculations requires a double integration extending over the primary and secondary energy groups, where, for a given initial energy, the integration over the secondary energy group may be replaced by an integral over the possible scattering angles. In the present work, analytic expressions for these angular integrals are derived which are free of truncation error. Differences between the present method (as implemented in ROLAIDS) and other methods (as implemented in MINX and NEWXLACS) are explored. Of particular interest is the fact that, for hydrogen, the angular integration is shown to simplify to the point that, for many weight functions, the integration over the primary energy group might also be performed analytically. This completely analytic treatment for hydrogen has recently been implemented in NEWXLACS. 1 figure.

The purpose of this publication is to provide instructions for the development of EEO Plans for Fiscal Year 1979. It supplements the National EEO Plan for the Department of Energy issued in August 1978 (DOE/S-0002). The material included should be used immediately as guidance to develop, document, and implement subordinate echelon commitments to EEO. A schedule for the development and submission of EEO Plans is included. Most of the continuing requirements will be published at a later date as part of the directives system. Any comments or helpful suggestions concerned with the program outlined would be appreciated by the Office of Equal Opportunity.

Progress of the major government sponsored projects undertaken to increase gas production from the low permeability gas sands of the western United States during February, 1978 is summarized. The Western Gas Sands Project files, which contain raw data and published reports from each Western Gas Sands Project participant have been established. A log file containing logs from pertinent wells in the four study areas has also been established. The U.S. Geological Survey (USGS) is continuing geological and geophysical studies in the four study areas for resource assessment. A number of papers giving results of recent investigations were presented at meetings during the month. The Bartlesville Energy Research Center (BERC) and participating National Laboratories are continuing their work in research and development. Field tests and demonstrations continue in the Uinta and Piceance Basins at the following locations: Uinta Basin, Gas Producing Enterprises, Inc. (GPE) Natural Buttes Unit Wells No. 14, 18, 19, 20, 21, and 22; Piceance Basin, Mobil Research and Development Corporation Well No. F-31-13G, Rio Blanco Natural Gas Company Well No. 498-4-1.

A flexible test system is studied and proposed to provide an extensive evaluation and testing capability for telemetry products. A distributed computer controlled, modular unit test system using Computer Automated Measurement and Control (CAMAC) standard hardware and compatible software is selected because of its flexibility of application and long term cost effectiveness.

The rotation and internal excitation limits of stability of superheavy compound nuclei (formed, for example, by heavy-ion collisions) are studied. The work is based on a macroscopic-microscopic description of the deformation of a nucleus. The two-center shell model for fission is generalized to include rotation (microscopic description) and internal excitations (statistical description). The physical basis for this study is described and the calculated results of the stability of fission barriers of superheavy elements are presented.