Report on methods to develop south Texas economically, includes grant and loan applications, fund appropriations, revenue bonds, more investment in banks in the area, amendments, and more.

This report describes the creepdown phenomenon in Zircaloy fuel cladding and the methods by which it will be measured and analyzed. Instrumentation for monitoring radial deformation in the cladding is described in detail--in terms of theory, design, and stability. The programs that control the microcomputer are listed, both to document the level of sophistication of the instrumentation and to indicate the flexibility of the test equipment.

This manual provides rough guidelines to aid a programer in installing ADBMS at a computer installation. ADBMS is a set of subroutines which together form a nucleus of a CODASYL-based data base management system. The use of this system is explained in detail in ''ADBMS Users Guide'' by E.W. Berss, Lawrence Livermore Laboratory, Feb. 1977.

A coordinated program for the development of improved cements specifically designed for geothermal well applications was continued. Polymer cements (PC) have been identified as promising well cementing materials. Tests indicate that at temperatures above 218/sup 0/C (425/sup 0/C) only PC materials containing mixtures of silica and portland cement are durable to brine and steam. Differential thermal analysis (DTA) studies are underway to determine the reason. Tests are also being conducted on two monomer systems that may further extend the operating temperature range. (JGB)

The DT fusion neutron irradiation of eight LLL Nb-1Zr tensile specimens, eleven BNL-LASL superconductor wires, one BPNL wire-foil packet, two ORNL magnesium oxide crystals, four LASL high purity single crystals, one each of spinel, YAG, Al/sub 2/O/sub 3/ and MgO, one LLL bicrystal of LiF and several LLL glass microscope cover slides is described. The sample position, beam-on time and dose record are given. The maximum neutron fluence on any sample was 2.51 x 10/sup 17/ neutrons/cm/sup 2/.

A separate abstract was prepared for each of the four sections. Two of these abstracts are included in Energy Abstracts for Policy Analysis (EAPA). (MOW)

An energy flow diagram for the U.S. for 1976 is presented, and one for 1975 is included for comparison. Some significant differences between 1975 and 1976 are: total energy use increased 4.8 percent, almost reaching the record use of 1973; oil imports increased significantly to 15.5 quads, more than 20 percent above 1975, and almost 44 percent of our total oil use; coal and natural gas remained more or less constant; by the author's reckoning, the industrial sector was unique in that its energy use decreased somewhat due to conservation efforts; delivered nuclear power increased by 10.9 percent and a trend toward electrification continued with distributed electrical energy increasing by 6.1 percent. (MCW)

The ENFORM system of computer codes can be used to calculate the amount of fuel material in the nuclear fuel cycle as a function of time. The material amounts are determined by an input schedule of installed electric energy generation capacity. In addition to the amount of uranium and plutonium in the fuel cycle, the system also accounts for 175 radionuclides. The effect of the fuel cycle on the environment can be calculated for the release of radionuclides and chemicals. The released radionuclides are modeled through the use of release factors and dose coefficients applied to the contained isotopic inventories. The chemical effluents released to the environment are modeled by using simple release factors. All release factors and dose coefficients are specific for each type of plant in the nuclear fuel cycle. The material logistics and effluent accounting features of the ENFORM system are supplemented by a fuel cycle economics package. This module provides fuel cycle processing costs and the levelized cost of power. The ENFORM system also provides means of estimating the effect of changing nuclear growth scenarios and changing environmental control technologies on nuclear fuel cycle effluents, economics and logistics.

The electrical resistivity, thermal conductivity, and Seebeck coefficient of three hydrogen doped high purity vanadium rods have been measured during heating from 77 K to 300 K. Correlations are made of the anomalous effects observed in two of the samples with the temperature of transformation from a hydride in a solid solution matrix to a solid solution. An increase in electrical resistivity is observed after thermal cycling but no apparent change in transformation temperature was observed.

Sintered alumino-silicate bodies, containing mullite as a principle phase, were tested in compression loading at 1200/sup 0/C. The observed mechanical behavior was correlated with the microstructure.

The Molten Core--Concrete Interactions Study was initiated on July 15, 1975, to provide a qualitative, extensive exploration of the phenomena associated with contact between molten-core materials and concrete. The experimental elements of this study are divided into four categories: (1) deposition of corium-type melts onto concrete, (2) kinetics and stoichiometry of the thermal decomposition of concrete, (3) response of concrete to heat fluxes at one surface, and (4) simulation experiments that explore phenomena at the interface between a melt and a decomposing solid. Experimental results are being incorporated in a scaling analysis that will establish scaling parameters for the system and identify key elements of the melt-concrete interaction. A number of major tests were performed during this period. Six large-scale molten steel/concrete interactions were performed to complete the test series. Several small-scale thermite melt/concrete tests were performed. The test series concerning the response of concrete to high heat flux was completed. Additional tests were performed concerning the thermal decomposition of concrete.

Absolute reaction rate theory is applied to explain the increased time between successive synchronous mitotic division of the slime mold Physarum polycephalum when exposed to extremely low frequency electromagnetic fields. By ignoring the transition period from the normal (control) mitotic cycle to the lengthened mitotic cycle of exposed P. polycephalum, the change in the activation energy is established. This activation energy is in the range of enzyme-catalyzed reactions. The influence of changing frequency on the above transition period is considered to complete the model.

The objective of the research is to develop mathematical models to explain and correlate the experimental data concerning two-phase cocurrent upflow through packed beds, as found in the Synthoil reactor and the associated cold-model. Such correlations and understanding will be useful in scale-up as well as optimum design of the reactor.

A new, preliminary design has been identified for the tokamak experimental power reactor (EPR). The revised EPR design is simpler, more compact, less expensive and has somewhat better performance characteristics than the previous design, yet retains many of the previously developed design concepts. This report summarizes the principle features of the new EPR design, including performance and cost.

The Division of International Affairs of the Energy Research and Development Administration is assessing the long-range economic effects of energy research and development programs in the U.S. and other countries, particularly members of the International Energy Agency (IEA). In support of this effort, a program was designed to coordinate the capabilities of five research groups--Rand, Virginia Polytechnic Institute, Brookhaven National Laboratory, Lawrence Livermore Laboratory, and Pacific Northwest Laboratory. The program could evaluate the international economics of proposed or anticipated sources of energy. This program is designed to be general, flexible, and capable of evaluating a diverse collection of potential energy (nuclear and nonnuclear) related problems. For example, the newly developed methodology could evaluate the international and domestic economic impact of nuclear-related energy sources, but also existing nonnuclear and potential energy sources such as solar, geothermal, wind, etc. Major items to be included would be the cost of exploration, cost of production, prices, profit, market penetration, investment requirements and investment goods, economic growth, change in balance of payments, etc. In addition, the changes in cost of producing all goods and services would be identified for each new energy source. PNL developed (1) a means of estimating the demands for major forms …

This project seeks to bring about a more effective use of nuclear instrumentation in medical applications of radionuclides in developing countries by facilitating selection of the more appropriate applications, by stimulating the design of instruments capable of performing these applications satisfactorily under the conditions prevailing, and by encouraging improved maintenance. A research contract has been established with a group at Harvard Medical School which constitutes a pilot cost-effectiveness analysis of nuclear medicine applications in the context of a developing country; the results are expected to be available in a few months. Data on commercially available well-scintillation-counter systems, probably the single most vital instrument in a simple laboratory, have been collected and classified, and a prototype of a simple new instrument is being constructed in the Agency's laboratory. The potential and suitability of these numerous instruments will be appraised. The current capabilities and requirements for maintenance of nuclear instruments in developing countries have been reviewed by a group of consultants. A program to survey the maintenance situation in developing countries on a regional basis has been initiated.

Progress is reported in the following areas: fission product release and transport, primary coolant impurities, rapid graphite oxidation, structural evaluation, materials, safety instrumentation and control systems, and phenomena modeling and system analysis.

The DT fusion neutron irradiation of 319 samples during 19 irradiation periods (beam-on time of more than 1026 hours) is described. Experiments from 24 individuals representing 11 institutions are summarized. The numbers of the UCID dosimetry reports detailing each of the irradiations are given.

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A bibliography of 148 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1976 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are sorted by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.

Radioactive decontamination of a large rugged terrain on the NTS (Area 20) was undertaken during the Summer of 1976. Several decontamination methods were used and their effectiveness, as measured by the fraction of radioactivity remaining (FR), ranged from 10/sup -1/ to 10/sup -3/, depending upon the method used and type of terrain. Front end loading was most efficient in large relatively flat areas of fine grain, compact dirt with an FR of about 10/sup -2/. Shoveling and bagging achieved FRs of 10/sup -2/ in locations of fine grain, compact dirt. However, if dirt was coarse grain or gravel-like, the contaminated mud/water had seeped to considerable depths, making shoveling impractical. Flushing with water was the method chosen for rocky surfaces and was the primary method of decontamination in Area 4. FRs down to 10/sup -3/ were achieved on smooth surfaces and about 10/sup -1/ in cracks. Vacuuming was very effective in flat areas with fine grain compact dirt achieving FRs down to 10/sup -3/, but was a very slow process compared to front end loading. Approximately 900 man days were expended on this cleanup, and 2584 yd/sup 3/ of contaminated dirt were removed. A similar amount of clean dirt was transported …

The first in a series of quarterly progress reports on ERDA budgeted activities subcontracted to Allied Chemical Corporation at the Idaho National Engineering Laboratory is presented. The work is performed by the Technical Division and is divided into three subjects. Fuel cycle research and development includes fluidized-bed calcination and post treatment of commercial nuclear fuel process waste; the storage of fission product noble gas; the catalyzed reaction between NO/sub x/ and NH/sub 3/; the adsorption and storage of /sup 129/I; evaporation of radioactive wastes; the removal of actinides from commercial high-level waste; reprocessing and waste treatment of HTGR fuel; and studies on natural fission reactors. Special materials production covers long-term management of ICPP high-level waste; ICPP fuel process improvements; advanced graphite fuels reprocessing; buried pipeline transfer systems; and ICPP waste management assistance. Other projects supporting energy development include geothermal energy development; inplant source term measurements; burnup methods for FBR fuels; nuclear materials security; absolute thermal fission yield measurements; analytical support to LWBR program; research on analytical methods; and environmental iodine species behavior.

The status of a program to determine the feasibility of a lithium--air battery (or an analog) as an automotive power source is summarized. Anticipated performance of characteristics (including efficiency and voltage) of the battery and the lithium recycling process are described. A calcium/aqueous-electrolyte combination was discovered which shows electrode behavior similar to that of Li. 2 figures, 2 tables.