THI3D-1 is an improved version of the THI3D computer program for steady-state, single-phase, thermal-hydraulic multichannel analysis. The program accounts for conservation of mass, energy, and momentum subject to pressure-drop boundary conditions, and leads to a nonlinear multipoint boundary-value problem. Turbulent interchange, radial thermal conduction, and forced flow due to wire wraps or grids between channels are explicitly taken into account. Temperature distributions in the coolant, cladding, fuel, and duct wall and the size of the central void of the oxide fuel after thermal restructuring are computed. Also included are program-input description and format, and a sample problem reflecting these improvements.

The R3 was the first of the R-series fuel-element meltdown tests performed to support modeling and code development for analysis of hypothetical, whole-core accidents in LMFBRs. Test R3 served as a proof test for the subsequent R4-R8 sequence of seven-pin tests examining coolant, cladding, and fuel behavior under thermal and hydraulic conditions representative of a hypothetical loss-of-coolant (LOF) with failure to scram in FFTF.

As a result of these meetings, the Geologic Review Group made suggestions and recommendations on radioactive waste repository sites, covering priorities for needed data on rock types, retrievable storage, use of Nevada Test Site, non-salt rock types, etc.

This brochure is designed as a basic source of information for prospective users of Sandia Laboratories Radiation Facilities. It contains a brief description of the various major radiation sources, a summary of their output characteristics, and additional information useful to experimenters. Radiation source development and source upgrading is an ongoing program, with new source configurations and modes of operation continually being devised to satisfy the ever-changing radiation requirements of the users. For most cases, the information here should allow a potential user to assess the applicability of a particular radiation facility to a proposed experiment and to permit some preirradiation calculations and planning.

The experimental results obtained from investigation of the radionuclide distribution in the environment around the detonation point of the 0.75-kt nuclear test, Cambric, fired 300 m underground in alluvium at the Nevada Test Site in 1965, are presented and discussed. Analyses of sidewall cores obtained ten years later from near ground surface to below the explosion cavity showed that most of the radioactivity is still contained within solid material in the lower cavity region. Water pumped from the region of highest activity at the bottom of the cavity showed only T and {sup 90}Sr at levels higher than the recommended concentration guides for drinking water in uncontrolled areas. Recommendations for future studies are given. The investigation is part of the Radionuclide Migration Project sponsored by the Nevada Operations Office of ERDA.

This report describes the methodology for determining where environmental control technology is required for the nuclear fuel cycle. The methodology addresses routine emission of chemical and radioactive effluents, and applies to mining, milling, conversion, enrichment, fuel fabrication, reactors (LWR and BWR) and fuel reprocessing. Chemical and radioactive effluents are evaluated independently. Radioactive effluents are evaluated on the basis of maximum exposed individual dose and population dose calculations for a 1-year emission period and a 50-year commitment. Sources of radionuclides for each facility are then listed according to their relative contribution to the total calculated dose. Effluent, ambient and toxicology standards are used to evaluate the effect of chemical effluents. First, each chemical and source configuration is determined. Sources are tagged if they exceed existirrg standards. The combined effect of all chemicals is assessed for each facility. If the additive effects are unacceptable, then additional control technology is recommended. Finally, sources and their chemicals at each facility are ranked according to their relative contribution to the ambient pollution level. This ranking identifies those sources most in need of environmental control.

The experiment requirements and objectives for the reactivity initiated accident (RIA) tests to be conducted in the Power Burst Facility (PBF) are described 1n the RIA Experiment Requirements Document (ERD) The primary objectives of the RIA research are to determine fuel failure thresholds, modes and consequences as functions of enthalpy insertion, irradiation history, and fuel design. Coolant conditions of pressure, temperature, and flow rate that are typical of hot-startup conditions in commercial BWRs will be used in the Series 1 tests. The first R!A test outlined in the ERD, RIA 1-1, is to be performed using four test fuel rods (two unirradiated and two irradiated) in the four rod hardware. The test fuel rods are to be exposed to a power transient in PBF which deposits an anergy of about 300 cal/g at 90% of the fuel radius (i.e. near the fuel surface). This will be the first RIA experiment ever perfonned at hot startup conditions and three potential problems have been identified since the ERD was written. These problem areas are: identification of the fuel failure threshold energy deposition for hot-startup conditions, evaluation of calorimetry techniques for RIA transient tests, and determination of possible pressure pulses that can result …

The Wind Characteristics Program Element (WCPE) is a service element to provide meteorological information to other parts of the Wind Energy Conversion Program. In this role, the WCPE has as its general objective acceleration of the development, commercialization and utilization of reliable and economically viable wind energy conversion systems (WECS). This report discusses the work undertaken in the areas of design and performance evaluation, site selection, and presiting evaluation from April 1976 through June 1977. A systematic evaluation of wind descriptors has begun in the Design and Performance Evaluation Program Areas and is leading to the preparation of handbooks of meteorological information for use in design and performance evaluation. A conceptual framework has been established within the Site Selection Program Area that clearly defines the relationships between siting tools. The Presiting Evaluation Program Area is involved in the identification of large areas of high wind energy potential throughout the United States, and in the determination of wind characteristics related to the economic viability of wind energy conversion within these areas.

The current status of Reactivity Initiated Accident (RIA) irradiated fuel behavior knowledge, based primarily on the review of the NSRR and SPERT data and the fuel rod modeling studies presented in the Experiment Requirements Document (ERD), is discussed. The hardware specifications are provided, including the test assembly and the test rods. The measurement requirements needed to meet the objectives of the test are presented. Some of the reactor operation requirements associated with the RIA 1-2 test are listed.

The objective of this study is to perform a synthesis of existing national wind energy assessments t o develop an improved consistent assessment of the geographical distribution of the available wind power over the United States. Previous national wind energy assessments have been reviewed with respect to techniques, assumptions, data sets/summaries, and interpolation schemes used. The overall representativeness of the resource maps produced has been evaluated Discrepancies exist among 'previous assessments with regard to geographical variations and the estimated values of wind power. Information from the existiqg national wind energy assessments and various other sources has been selectively used to form a synthesized national assessment. As part of the synthesis, additional research was performed to further improve the national assessment. This included a more detailed examination of some of the inherent problems with respect to the representativeness and reliability of the surface and rawinsonde wind data, techniques employed in the vertical extrapolation of wind power, in the estimation of wind power over mountainous and offshore areas and areas of sparse data, and in the analysis and interpolation of the values.

This workshop was the sixth of a series and was held on July 11 and 12, 1977, at the Oak Ridge National Laboratory in Oak Ridge, Tennessee. Those presenting papers at the Sixth Workshop prepared summary reports of their recent work for inclusion in this document. The reports are reproduced here as submitted by the participants, with only minor editing. This year's Workshop took a decidedly international flavor, with participants from seven countries in addition to the United States. The significance of this group's contributions has raised the possibility that the next Neutron Dosimetry Workshop may be held in Europe. Of particular interest at the Workshop was the keynote address by Dr. Harald Rossi. He commented that there is evidence that 1) accepted values of RBE for low absorbed doses of neutrons may be low by an order of magnitude or more and 2) the risk of leukemia is significant at 0.5 rad to the bone narrow. A reduction of the limit for permissible neutron exposure, which could result from consideration of this information, would necessitate major improvements in our "middle ages" neutron dosimetry. A number of participants reported conversions to thermoluminescent dosimeter (TLD) systems. This move has not been …

This report is to be used by Utah Power and Light Company (UP and L) in making studies of geothermal power plants. The dollars per kilowatt comparison between a geothermal plant and a UP and L coal-fired plant is to be developed. Geothermal gathering system costs and return to owner are to be developed for information.

This environmental impact assessment (EIA) addresses the expected programmatic activities of the Geopressure Subprogram of the Division of Geothermal Energy. The goal of the Geopressure Subprogram is to stimulate development of geopressured resources as an economic, reliable, operationally safe, and environmentally acceptable energy source. The subprogram includes activities in the areas of engineering research and development; resource exploration, assessment, and development; resource utilization including pilot and demonstration facilities; and environmental research and control technology development. It should be recognized that most of the subprogram activities extend over several years and are in their early stages of implementation at this time. The zones of potential geopressure development are in the region located along the Texas and Louisiana Gulf Coasts extending up to 200 miles (300 km) inland. Geopressured zones are sedimentary basins where water is trapped at high pressures within or below thick, nearly impermeable shale sequences. The confined water supports most or all of the weight of the overburden. This inhibits sediment compaction and causes formation pore pressure to exceed hydrostatic pressure. in sedimentary basins that are underlain by thin oceanic crust, upward thermal conduction from the mantle heats geopressured fluids and sediments to abnormally high temperatures, often in excess …

From introduction: The purpose of the study was to describe the differences between ponds that developed within and abandoned mine site and in control ponds not affected by mining.

Abstract: Nine artificial-recharge pits were excavated in the alluvium in upper Black Squirrel Creek basin, Jimmy Campy Valley, and in the alluvium overlying the Widefield aquifer in Fountain Valley. Each artificial-recharge site was instrumented to measure inflow, stage fluctuations, and water-table fluctuations. Artificial-recharge tests conducted in upper Black Squirrel Creek basin indicated that the average adjusted rates of infiltration for the three sites ranged from 1.6 to 2.4 feet (0.5 to 0.7 meter) per day. Tests conducted in Jimmy Camp Valley indicated that the average adjusted rates of infiltration for the two sites ranged from 3.8 to 24.7 feet (1.2 to 7.5 meters) per day. Tests conducted on the Widefield aquifer indicated that the average adjusted rates of infiltration for four sites ranged from 2.3 to 12.9 feet (0.7 to 3.9 meters) per day.

This report contains information regarding the assassination of President John F. Kennedy in 1963, including knowledge about what happened before and after the event.

This report is a religious discrimination in employment.

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From introduction: This report presents engineering details, history, well logs, and a brief geologic interpretation of the Carson Sink, Nevada, drilling program. A geologic report is in preparation and the geologic information contained herein is of a preliminary nature.

Three investigations of difference frequency generation (DFG) of far-infrared radiation by optical mixing are described: a theory of DFG by monochromatic, focused Gaussian pump laser beams, a theory of DFG by a picosecond pump laser pulse, and an experiment using ruby-pumped dye lasers. First, the theory of far-infrared generation by optical mixing of monochromatic, focused Gaussian beams in a uniaxial crystal is developed, taking into account the effects of diffraction, absorption, double refraction, and multiple reflections and total reflection at the boundary surfaces. (Reflection and transmission coefficients of a uniaxial crystal slab are derived by a new matrix technique.) Results of numerical calculations are presented. Focusing the pump beams appreciably enhances the far-infrared output despite the strong far-infrared diffraction. In a 1-cm long crystal, the optimum focal spot size is approximately equal to or smaller than the far-infrared wavelength for output frequencies less than 100 cm{sup -1}. Double refraction of the pump beams is relatively unimportant. Both far-infrared absorption and boundary reflections have major effects on the far-infrared output and its angular distribution. The former is often the factor which limits the output power. We show that a simple model treating the nonlinear polarization as a constant lie-radius Gaussian distribution …

Evaluation of the application of heavy ion accelerators to ignite d-t pellets in a thermonuclear reactor is discussed. Accelerator design requirements considered include transport-limited current, beam injection conditions, and pulse bunching and focusing characteristics. The desirability of resonant and non-resonant accelerating structures is comparatively examined. The required power system switch tubes are discussed. It is concluded that heavy ion accelerators could offer a promising solution to the pellet-igniter problem. The advantages pointed out for this approach include electric efficiency greater than 10 percent, the possibility of high repetition rates (1 to 10 Hz), and a mature technological base. (RME)

One of the most important factors in isolating the demonstration waste storage site is an adequate number of shafts to insure proper ventilation. Proper ventilation will require that the air exhausted from the storage area pass directly to the upcast air shaft. Those mines reported by this scoping contract generally conform with the two shafts per mine requirement of MESA. Three of the mines reported on have more than two shafts. Several of the mines can have additional shafts drilled in time to meet ERDA's schedule. Rough drilling costs have been cited in the report. From an economic standpoint, it is probable that the larger the mine, the greater the economic impact with regard to any dislocation of production that may be required. In some cases, such as the Retsof Mine and the Cayuga Mine, multiple shafts eliminate the probability of dislocation. Those small tonnage mines such as the Kleer at Grand Saline, Texas; the Hockley Mine near Houston and the Lyons Mine of the American Salt Company might be leased or purchased in their entirety.

The development of economic data for fusion power plants continued in a study estimating the potential impact of a shortage of materials important in fusion plant construction. In studies developing heat transfer and fluid flow design tools for fusion reactor blankets, preconceptual design studies were initiated to identify the potential design limits of water cooling in the first wall of Tokamak Next Step (TNS) concepts. In surface effects research clean gold samples were irradiated in the University of California (D,Be) neutron source for a neutron sputtering experiment. Light ion and neutron irradiation experiments have continued in studies of the effects of radiation on mechanical properties. The hardening response of 14 MeV neutron-irradiated nickel changed at high particle fluences (10/sup 16/ to 10/sup 17/ particles/cm/sup 2/) while the hardening response of 16 MeV proton-irradiated nickel did not, which may have been due to a difference in irradiation hardening mechanisms. The flux dependence of the damage microstructure and irradiation hardening of materials needs further study to clarify uncertainty about light ion and fusion neutron damage processes. Neutron irradiations of Ni, 316SS, and Nb wires and foils were completed. Work has continued in studies developing acoustic emission (AE) techniques for determining the prebreakdown …

A new concept for a power breeder reactor that consists of an accelerator-driven subcritical thermal fission system is proposed. In this system an accelerator provides a high-energy proton beam which interacts with a heavy-element target to produce, via spallation reactions, an intense source of neutrons. This source then drives a natural-uranium-fueled, light-water-moderated and -cooled subcritical blanket which both breeds new fuel and generates heat that can be converted to electrical power. The report given presents a general layout of the resulting Accelerator Driven Light Water Reactor (ADLWR), evaluates its performance, discusses its fuel cycle characteristics, and identifies the potential contributions to the nuclear energy economy this type of power reactor might make. A light-water thermal fission system is found to provide an attractive feature when designed to be source-driven. The equilibrium fissile fuel content that gives the highest energy multiplication is approximately equal to the content of /sup 235/U in natural uranium. Consequently, natural-uranium-fueled ADLWRs that are designed to have the highest energy generation per source neutron are also fuel-self-sufficient; that is, their fissile fuel content remains constant with burnup. This feature allows the development of a nuclear energy system that is based on the most highly developed fission technology …