Volume contains the maps and charts generated during the hydrocarbon evaluation of the proposed radioactive material storage site in southeastern New Mexico. (LK)

A description of the Geothermal Loop Experimental Facility (GLEF) its construction problems, and a discussion of start-up testing are included. A history and description of the operation and maintenance with the brine injection pump for the facility are presented. The GLEF was divided into five separate sections: steam and condensate system, brine system, purge water system, vent gas system, and cooling water system. An insight into the chemistry of each system is provided by analysis of samples taken. Scaling and corrosion effects of brine, steam, gas, and water in these systems are described in detail. (MHR)

It is concluded that the direct effects of an ideal form of fusion technologies would be socially more desirable than those of the alternatives. This is particularly true of the second generation fusion power plant. However, given our technological inputs, this was a trivial result. Less trivial was consideration of the negative effects that might accrue through the availability of potentially unlimited supplies of low cost energy. It is concluded that while there may be reasonable humanist argument both for and against such abundance, in a democratic society control of energy development for its own sake is likely to be unacceptable. However, if the indirect effects of pollution, despoilment, and resource depletion through ever expanding energy use become sufficiently disturbing to the well-being of the majority, unlimited energy may come to be seen as undesirable by the society. To this extent successful research and development for unlimited sources such as the fusion or mixed solar alternatives might be judged from some point far in the future to have been a mistake. This could occur even though advances in the technology of pollution control and resource use greatly reduce the pollution and hazard accompanying a much higher rate of energy utilization.

Work during the period was devoted primarily to a range of analytical/numerical investigations, including evaluation of means to improve external blanket designs, beneficial attributes of the use of internal blankets, improved methods for the calculation of heterogeneous self-shielding and parametric studies of calculated spectral indices. Experimental work included measurements of the ratio of U-238 captures to U-235 fissions in a standard blanket mockup, and completion of development work on the radiophotoluminescent readout of LiF thermoluminescent detectors. The most significant findings were that there is very little prospect for substantial improvement in the breeding performance of external blankets, but internal blankets continue to show promise, particularly if they are used in such a way as to increase the volume fraction of fuel inside the core envelope. An improved equivalence theorem was developed which may allow use of fast reactor methods to calculate heterogeneously self-shielded cross sections in both fast and thermal reactors.

Literature reviews indicate that existing information is incomplete, often contradictory, and of questionable value for the prediction and assessment of ultimate impact from fusion-associated activation products and other chemical releases. It is still uncertain which structural materials will be used in the blanket and first wall of fusion power plants. However, niobium, vanadium, vanadium-chromium alloy, vanadium-titanium alloy, sintered aluminum product, and stainless steel have been suggested. The activation products of principal concern will be the longer-lived isotopes of /sup 26/Al, /sup 49/V, /sup 51/Cr, /sup 54/Mn, /sup 55/Fe, /sup 58/Co, /sup 60/Co, /sup 93/Nb, and /sup 94/Nb. Lithium released to the environment either during the mining cycle, from power plant operation or accident, may be in the form of a number of compound types varying in solubility and affinity for biological organisms. The effects of a severe liquid metal fire or explosion involving Na or K will vary according to inherent abiotic and biotic features of the affected site. Saline, saline-alkaline, and sodic soils of arid lands would be particularly susceptible to alkaline stress. Beryllium released to the environment during the mining cycle or reactor accident situation could be in the form of a number of compound types. Adverse effects …

Commercial tubing for LMFBR sodium-water steam generator applications was produced from ESR and VAR 2/sup 1///sub 4/Cr--1Mo alloy (Grade T22) and characterized regarding chemical composition, microstructure, physical characteristics, and short and long term mechanical properties. These results demonstrate that tubing meeting RDT Standard RDT M3-33 can be produced from either the ESR or VAR process and is acceptable to ASME Code Section III requirements. Metallurgical and mechanical properties are similar for both ESR and VAR material, indicating that either remelting practice is acceptable.

Discussions of both known data losses and how they occured, and of diagnostic methods used to detect sensor faults are presented. Measures taken to reduce both data losses and sensor faults are also discussed. Appendix A presents: lists of dates for which 24 hours of data were recorded, lists of dates and hours for which data is missing, and lists of dates and hours for which partial sets of data were obtained due to failure of the data acquisition system. Appendix B contains lists of observations and actions pertinentsor faults.

Vacuum are remelting (VAR) and electroslag remelting (ESR) processes for steam generator tubesheet forgings and tubing are to be used at the CRBR. It was found that there is essentially no significant effect on the uniaxial tensile properties of 2 1/4 Cr-1Mo steel by VAR or ESR. A summary is presented of results of a study of heat treatment combined with post weld heat treatment. It was found that regardless of the primary heat treatment, the post weld heat treatment plus in-service conditions will reduce the yield strength at elevated temperature below the Code Case expected minimum curve. (FS)

This report describes the RTG degradation mechanisms which have been identified as occurring in thermoelectric power generating systems that use the alloy of silicon germanium as the thermoelectric material and that incorporate a multifoil thermal insulation system. The synergetic effects of all of the identified degradation mechanisms are determined by a computer code, DEGRA, which calculates the available generator output power as a function of generator operating time.

Model validation is the process of determining if the model actually represents the system that it was intended to model. The results obtained by applying outlined procedures to validate four simulation models of solar heated buildings are presented. These models are SOLSIM, SOLCOST, TRNSYS, and SIMSHAC. The scope of the work, summary of important results, and conclusions and recommendations are presented. Appendices contain detailed discussions of the methodology and detailed validation results. (MHR)

The Thermal Storage Subsystem Research Experiment is designed to give maximum information for evaluating the design, performance, and operating parameters of the Barstow Solar Pilot Plant. The experiment is summarized, and the experiment components detail design and integration are described. The experiment test and operation is described which is designed to collect engineering data to allow the design, performance, and operational characteristics to be specified for the Pilot Plant. Appended are: design documentation; pressure drop calculations; materials studies for thermal energy storage; flow charts for data acquisition and control; condenser detail design; instrumentation error analysis; logic diagrams for the control system; literature survey to evaluate the two-phase forced convection heat transfer; and the vaporizer performance model. (LEW)

Procedures followed and equipment used in completion of the well to 6,455 feet are described. (MHR)

This document, which covers the period January 1-June 30, 1976, describes progress in the following areas: (1) advanced analytical techniques for the clinical laboratory, (2) fast clinical analyzers, (3) development of a miniaturized analytical clinical laboratory system, (4) centrifugal fast analyzers for animal toxicological studies, and (5) chemical profile of body fluids.

Crater data from numerous high-explosive (HE) experiments and from fewer nuclear explosive (NE) tests are used to develop an empirically based procedure for predicting crater dimensions from nuclear explosions in various geologic media. The HE crater data are used to rank the cratering efficiency of various geologies. NE crater data from dry soil at the Nevada Test Site and from saturated coral at Eniwetok and Bikini atolls are used to relate NE and HE cratering efficiency. Crater shapes from explosive and impact craters are examined to provide a basis for estimating crater radius and depth in a given geology once the crater volume is known. Best estimates of the crater volume and dimensions are presented along with an estimated range of uncertainty.

Due to the extensive nature of this study, the report is presented as a series of small reports. The complete design analysis is placed in a separate section. The drawings and tabulations are in the back portion of the report. Other topics are enumerated and located as shown in the table of contents.

The objectives of this study are: (1) to develop a marine industry profile in terms of equipment, operating characteristics, energy consumption, costs and develop performance measurements in terms of ton-miles per BTU or operating hours per BTU for each industry sector identified; (2) to identify the role of all government and quasi-government agencies that impact the Marine Industry, projecting changes in the regulatory structure; to evaluate the energy use impact of these existing and proposed regulations; (3) to identify existing and expected R and D programs in those areas that impact the marine industry and fuel consumption; to evaluate the market for new technologies and the expected energy impact of the more prominent technologies; to estimate the cost of these R and D programs together with the cost of implementing the new technology; and (4) to evaluate alternative industry futures in the operational, regulatory and technological areas to determine the overall energy impact of each likely combination. The project schedule is presented and progress on Task 1 is reported.

A model for a windowed, high-temperature cavity receiver of the heated-air type is developed and used to evaluate the greenhouse effect as a method for obtaining high receiver operating efficiencies. The effects on receiver efficiency of varying the window cutoff wavelength, the amount of absorption in the window pass-band, the cavity operating temperature, and the number of windows are determined. Single windowed cavities are found to offer theoretical efficiencies comparable to windowless ones, while multiple windowed units are found to suffer from low operating efficiencies due to losses resulting from reflections at each window/air interface. A ''first order'' examination is made of the feasibility of air cooling the window to assure its survival. This appears possible if a proper combination of cooling technique and window material characteristics is selected.

The purpose of this study is to assess tritium control aspects of fusion reactors, to derive a preliminary estimate of the probable tritium releases and source terms under steady-state reactor operation, and to identify areas where advancement of fusion reactor tritium control technology will be required. Tritium release aspects of six fusion reactor conceptual designs were evaluated, including four Tokamaks, one mirror and one theta pinch reactor. The principal effort was directed to Tokamaks because they represent the current main-line Division of Magnetic Fusion Energy (DMFE) effort. Two tokamaks which had the most detailed conceptual designs at the time of the analysis (PPPL and UWMAK-I) were selected for detailed analysis to define tritium source terms.

Radioactive fallout from this Chinese nuclear test resulted in measurable deposition of short-lived debris over much of the United States. The fallout levels varied by more than 1000-fold and showed significant temporary or spatial fractionation with higher levels of deposition being associated with rain. The particle size with which the airborne debris was associated decreased continuously with time following detonation and a substantial fraction of the {sup 131}I was associated with inorganic and organic gases. The potential radiation dose to an infant consuming milk produced at the location of the highest concentration of {sup 131}I measured on grass was estimated to be {approximately}l rem. This dose is about 50 times the annual dose received in the vicinity of a power reactor operating under the existing US Nuclear Regulatory Commission design guides. The potential upper limit thyroid dose for the population of 17 eastern seaboard states from this single test was estimated to be about 2.4 {times} 10{sup 6} man-thyroid-rem under the assumption that all dairy cows remained on fresh pasture throughout the month following the initial decomposition of fallout debris. This dose is about 200 times the estimated dose from currently operating nuclear power reactors and about 50 times the …

An enclosure to protect instrumentation packages from the severe pressure and temperature environment presented by downhole conditions at the LASL Q-12 Division Fenton Hill Geothermal Research site is specified. Due to a general lack of interest by prospective vendors in handling all phases of the design and fabrication, a pressure vessel housing was designed and specified for their use in establishing the thermal insulation and heat sink requirements. Included are specifications recommended for use in purchasing the pressure vessel material and in specifying the important thermal parameters and size limitations.

The Mortran processor was slightly modified, and a new set of macros was written, to act as an aid in the translation of IBM Fortran programs to CDC Fortran. A 30,000-source-card program was successfully converted by using the resulting package. The capabilities and limitations of this approach to Fortran conversion are described, and two examples of the output of the package are given.

Two contract modifications (one to study the effect of reactor design on bioconversion efficiency and the other to study the effects of variable speed mixing) are reported. All equipment has now been obtained, but installation is not complete. (JSR)

A project undertaken to determine the ink characteristics affecting fired films is described. The analytical methods used were thermogravimetric analysis, pryolysis-gas chromatography, infrared spectrophotometry, mass spectrometry, atomic absorption spectrophotometry, scanning electron microscopy with energy dispersive x-ray spectroscopy, and particle size analysis using a Coulter counter.

The objective of the Pacific Northwest Regional Assessment Program is to estimate changes in the Region's environmental, socioeconomic, and health status that could result from various energy development or conservation scenarios. Battelle, Pacific Northwest Laboratories, uses a dynamic simulation model to help evaluate pertinent issues in the Northwest (Alaska, Idaho, Montana, Oregon, Washington, and Wyoming). One of the primary sectors of this model is the demographic sector, which provides the needed demographic information to other model sectors. Specifically, it traces the effects of various energy development scenarios on employment and population growth. The demographic sector simulates the interactions among the population, birth rate, death rate, net migration rate, and jobs available in the Region from 1960 to 2020. The population is disaggregated so that age-specific birth and death rates, age-specific propensity to migrate, and age-specific labor force participation rates can be used.