A hydrologic test system has been designed to measure the intrinsic permeabilities of individual fractures in crystalline rock. This system is used to conduct constant pressure-declining flow rate and pressure pulse hydraulic tests. The system is composed of four distinct units: (1) the Packer System, (2) Injection system, (3) Collection System, and (4) Electronic Data Acquisition System. The apparatus is built in modules so it can be easily transported and re-assembled. It is also designed to operate over a wide range of pressures (0 to 300 psig) and flow rates (0.2 to 1.0 gal/min). This system has proved extremely effective and versatile in its use at the Climax Facility, Nevada Test Site.

This Engineering Test Plan (ETP) describes field studies of radionuclide migration in fractured rock designed for the Climax grainite at the Nevada Test Site. The purpose of the ETP is to provide a detailed written document of the method of accomplishing these studies. The ETP contains the experimental test plans, an instrumentation plan, system schematics, a description of the test facility, and a brief outline of the laboratory support studies needed to understand the chemistry of the rock/water/radionuclide interactions. Results of our initial hydrologic investigations are presented along with pretest predictions based on the hydrologic test results.

The vadose zone in arid regions is considered as a possible environment for geologic isolation of nuclear waste. There are several topographic and lithologic combinations in the vadose zone of arid regions that may lend themselves to waste isolation considerations. In some cases, topographic highs such as mesas and interbasin ranges - comprised of several rock types, may contain essentially dry or partially saturated conditions favorable for isolation. The adjacent basins, especially in the far western and southwestern US, may have no surface or subsurface hydrologic connections with systems ultimately leading to the ocean. Some rock types may have the favorable characteristics of very low permeability and contain appropriate minerals for the strong chemical retardation of radionuclides. Environments exhibiting these hydrologic and geochemical attributes are the areas underlain by tuffaceous rocks, relatively common in the Basin and Range geomorphic province. Adjacent valley areas, where tuffaceous debris makes up a significant component of valley fill alluvium, may also contain thick zones of unsaturated material, and as such also lend themselves to strong consideration as respository environments. This paper summarizes the aspects of nuclear waste isolation in unsaturated regimes in alluvial-filled valleys and tuffaceous rocks of the Basin and Range province.

Sodium tetraphenylborate is used to coprecipitate cesium with potassium in the precipitation process that has been developed to decontaminate waste salt solutions. This report summarizes the results that have been obtained.

Leach testing experiments were conducted on SYNROC-D material to examine the parameters which affect leaching results and to measure the activation energy for leaching of elements from SYNROC-D. Measured leach rates were found to be controlled by precipitation of insoluble phases for those tests where the sample surface area to volume of leachant (SA/V) multiplied by leaching time (t) exceeded 0.3 cm{sup -1}d for leach tests at 90{sup 0}C. In these cases the apparent activation energy for leaching was approximately 10 kcal/mole based on Na and Si data. For leach tests at 90{sup 0}C with (SA/V)(t) less than 0.2 cm{sup -1}d, the activation energy for Na and Si dissolution was 18.5 kcal/mole for sample S29 and 14.5 kcal/mole for sample LS04. These activation energies are in agreement with values reported by Tole and Lasaga (1981) for nepheline dissolution. The effect of sample geometry was investigated by leaching a series of crushed samples of different grain size. The results support the view that geometric surface area should be used in leach rate calculations rather than gas adsorption BET surface area. Comparison of results on S29 leaching of crushed samples and monoliths show that data from MCC-1 and ISO type leach tests …

As an integral part of the Spent Fuel Test-Climax 5150 ft (1570 m) of granite core was obtained. This core was diamond drilled in various sizes, mainly 38-mm and 76-mm diameters. The core was teken with single tube core barrels and was unoriented. Techniques used to drill and log this core are discussed, as well as techniques to orient the core. Of the 5150 ft (1570 m) of core more than 3645 ft (1111 m) was retained and logged in some detail. As a result of the core logging, geologic discontinuities were identified, joint frequency and spacing characterized. Discontinuities identified included several joint sets, shear zones and faults. Correlations based on coring along were generally found to be impossible, even for the more prominent features. The only feature properly correlated from the exploratory drilling was the fault system at the end of the facility, but it was not identified from the exploratory core as a fault. Identification of discontinuities was later helped by underground mapping that identified several different joint sets with different characteristics. It was found that joint frequency varied from 0.3 to 1.1 joint per foot of core for open fractures and from 0.3 to 3.3/ft for closed …

Experiments on tri-n-butyl phosphate solvent extraction of uranium and plutonium at full activity levels (Campaigns 3 and 4) were conducted in the Solvent Extraction Test Facility (SETF), located in one of the heavily shielded cells of the Transuranium Processing Plant. The primary objectives were: (1) to demonstrate and evaluate the first two cycles of the Hot Engineering Facility flowsheets (codecontamination and partial partitioning), and (2) to investigate and evaluate the use of HNO{sub 2} as the reductant for tetravalent plutonium during reductive stripping operations. Secondary objectives were to determine the solvent extraction behavior of feed solutions prepared by dissolving fuel from a boiling water reactor (BWR) and to improve the solvent extraction feed clarification.

The first XUV and x-ray spectra were recorded from TEXT with a grazing-incidence grating spectrograph and new crystal spectrographs. Time- and space-integrated data yielded a qualitative description of the plasma. Line radiation from O, Cr, Fe, and Ni ions was recorded and identified with the aid of ab initio atomic structure calculations. Approximate values of plasma characteristics were obtained from the spectra. A derived electron temperature of 800 eV and electron density of 2 {times} 10{sup 13} cm{sup {minus}3} are consistent with results from other diagnostics. Spectrometers which will provide time- and space-resolved data are being designed for quantitative rate and transport studies.

This was the last of three companion cruises designed to provide broad-scale coverage of seasonal shelf conditions occurring between the April and October investigations undertaken aboard ATLANTIS II cruises 99 and 104.

Safety assessments and environmental impact statements for nuclear fuel cycle facilities require an estimate of the amount of radioactive particulate material initially airborne (source term) during accidents. Pacific Northwest Laboratory (PNL) has surveyed the literature, gathering information on the amount and size of these particles that has been developed from limited experimental work, measurements made from operational accidents, and known aerosol behavior. Information useful for calculating both liquid and powder source terms is compiled in this report. Potential aerosol generating events discussed are spills, resuspension, aerodynamic entrainment, explosions and pressurized releases, comminution, and airborne chemical reactions. A discussion of liquid behavior in sprays, sparging, evaporation, and condensation as applied to accident situations is also included.

The ISystemsl task of the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program is developing a Systems Approximate Simulator (SAS); a computer code of low-level technical complexity that incorporates the most significant waste-package, repository, and site processes affecting geologic nuclear waste isolation. This report discusses the AEGIS 1982 fiscal year progress toward building a SAS. A computer code, SAS(82), has been developed as the site module of the SAS development effort. The SAS(82) is an efficient and accurate simulator of one-dimensional radionuclide transport. Features of the SAS(82) are direct (Monte Carlo) simulation, linear decay and sorption models, spatially and temporally varying hydrologic and geochemical variables, general travel-time distributions (possibly non-Fickian), and multinuclide release. The SAS(82) was used to simulate radionuclide transport from a nuclear waste repository located within the Hanford basalts. A {sup 99}Tc analysis along a thermally influenced path through the Grande Ronde Formation demonstrated the complexity of modeling near-field transport. Perturbed hydrologic conditions corresponding to "Hanford Basalt Geologic Simulation Model" results (Petrie et al. 1981) were evaluated, using the SAS(82). Future work will include the development of SAS waste-package and repository modules as simplified process models become available. The SAS may eventually be used as the basis …

The upgrade and redesign of a fluidized-bed denitrator for production of uranium trioxide from uranyl nitrate solution is discussed. The success of the project in improving process efficiency and personnel safety is also addressed based on subsequent operation.

This report describes a direct-contacting liquid level and void fraction detection system that is being developed by Pacific Northwest Laboratory. The measurement technique could be used in the severe fuel damage tests that will be conducted at the Power Burst Facility, Idaho Falls, Idaho, and at the ESSOR reactor, Ispra, Italy. The detection system could also be retrofitted for commercial operating reactors to provide definitive thermal-hydraulic information. The technique can provide unambiguous, real-time data on liquid level and void fraction during normal reactor operation as well as during shutdown and accident conditions.

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This document contains data tables on microfiche of single particle inclusive cross sections of protons, deuterons, tritons, {sup 3}He, {sup 4}He, {sup 6}He, {sup 8}He, and {pi}{sup -}. The production of these fragments was measured in collisions of 1.05 GeV/A and 2.1 GeV/A proton, deuteron, alpha and carbon projectiles as well as 0.4 GeV/A alpha particles on targets of C, Cu, Pb, and H (from a CH{sub 2}-C subtraction), using a double focusing spectrometer. Only fragment emission in the region 0.5 {le} (p/Z){sub lab} {le} 8.7 GV/c and 0{sup o} {le} {var_theta}{sub lab} {le} 12{sup o} is included.

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In this report we describe the new two-phase flow facility that has been constructed at Brown University. Included is the design philosophy that led us to select a blow-down, Freon tunnel as the means of studying the flow of a pure substance undergoing liquid-vapor phase changes. Each component is discussed from the initial design considerations, through sizing calculations, to actual system specifications. Special emphasis is placed on the instrumentation and automatic data acquisition and processing system. Finally a sampling of results obtained so far is presented. Section 1 gives the reasons for the construction of the facility and lists some of the uses and objectives of its operation. The reader can gain a good overview of the facility from Section 2 without a great deal of detail. In Section 3 we present the rationale for the particular design choices that were made and give details about the selection and sizing of all major components except the instrumentation. The latter subject is treated in Section 4 where we discuss the temperature and pressure probes, mass flow rate measurement, and other instrumentation. Section 5 is devoted to the test section proper where all the two-phase flow measurements and observations take place. The …

Supply curves of conserved energy provide an accounting framework that expresses the potential for energy conservation. The economic worthiness of a conservation measure is expressed in terms of the cost of conserved energy, and a measure is considered economical when the cost of conserved energy is less than the price of the energy it replaces. A supply curve of conserved energy is independent of energy prices; however, the economical reserves of conserved energy will depend on energy prices. Double-counting of energy savings and error propagation are common problems when estimating conservation potentials, but supply curves minimize these difficulties and make their consequences predictable. The sensitivity of the cost of conserved energy is examined, as are variations in the optimal investment strategy in response to changes in inputs. Guidelines are presented for predicting the consequences of such changes. The conservation supply curve concept can be applied to peak power, water, pollution, and other markets where consumers demand a service rather than a particular good.

Radian received twelve sections of heat exchanger tubing from the Magma Electric Company's 10MW(e) East Mesa binary geothermal power plant. Three tube sections were received from each of four shell and tube heat exchangers (HX1, Hx6, HX8, and Hx10) of the isobutane vaporizer train. All samples were taken from the upper few rows of tubes. Two months later, four more tube sections were received. These four sections were taken from the lower rows of heat exchangers 1, 6 (two sections), and 10. Radian was requested to investigate the cause of severe pitting failure of these heat exchanger tubes. This report is part of a continuing DOE effort to gain insight into the service life of component materials employed in geothermal energy utilization.

Impurities in the Tandem Mirror Experiment (TMX) have been studied using extreme ultraviolet spectroscopy. Three time-resolving absolutely-calibrated normal-incidence monochromators, one on each section of TMX, were used to study the impurity emissions in the wavelength range of 300 A to 1600 A. The instruments on the east end cell and central cell were each capable of obtaining spatially-resolved profiles from 22 chords of the plasma simultaneously while the instrument on the west end cell monitored the central chord. The impurities identified in TMX were carbon, nitrogen, oxygen, and titanium. Emphasis was placed upon determining the impurity densities and radiated power losses of the central cell; results indicate that the impurity concentrations were low - less than 0.4% for each species - and that less than 10% of the total net trapped neutral beam power was lost to radiation. The use of titanium gettering on the central cell walls was observed to decrease the brightnesses of singly- and doubly-ionized carbon and oxygen in the central cell plasma. In the end cells, oxygen was the main impurity with a concentration of about 1.5% and was injected by the neutral beams; the other impurities had concentrations of about 0.5%. Radiation losses from the …

Ion cyclotron resonance heating (ICRH) was evaluated and it was found to be satisfactory for use in establishing the conditions necessary to form a thermal barrier in TMX-upgrade (TMX-U). We discuss the constraints that must be satisfied in order to maintain a plasma, and outline a complete startup scenario that ends with the plasma at design parameters. The detailed discussions in this report concentrate on those parts of startup where ICRH is necessary. The ability of ICRH to couple power into a plasma at the fundamental ion cyclotron resonance, w/sub ci/, is determined from experiments with a half-turn loop antenna in the Phaedrus tandem mirror central cell. From these experiments, we get the empirical scaling that shows power deposited in the plasma is proportional to the plasma density.

The Savannah River Plant has 28 ponds and 190 Carolina Bays on its 192,000-acreite. Excluding the Par Pond system, the mean pond area is 17.6 acre, with a range of 0.4 to 202.8 acres. Par Pond is the largest pond, with an area of 2500 acres. The mean Carolina Bay area is 6.6 acres, with a range of less than 0.3 to 124.0 acres. The geographical location of each pond and bay has been digitized and can be graphically displayed by computer. This capability will facilitate identification of wetland areas as required by Executive Order 11990 (Protection of Wetlands, May 24, 1977).

Geothermal development in The Geysers KGRA has affected local public services and fiscal resources in Sonoma, Lake, Mendocino, and Napa counties. Each of these counties underwent rapid population growth between 1970 and 1980, some of which can be attributed to geothermal development. The number of workers currently involved in the various aspects of geothermal development in The Geysers is identified. Using three different development scenarios, projections are made for the number of power plants needed to reach the electrical generation capacity of the steam resource in The Geysers. The report also projects the cumulative number of workers needed to develop the steam field and to construct, operate, and maintain these power plants. Although the number of construction workers fluctuates, most are not likely to become new, permanent residents of the KGRA counties. The administrative and public service costs of geothermal development to local jurisdictions are examined and compared to geothermal revenues accruing to the local governments. Revenues do not cover the immediate fiscal needs resulting from increases in local road maintenance and school enrollment attributable to geothermal development. Several mitigation options are discussed, and a framework is presented for calculating mitigation costs per unit of public service.

The following information about the Savannah River is tabulated: significant activities and discharges along the Savannah River, river water temperature data near Jackson st Savannah River Plant, flow informatiom, and reservoir parameters for Clarks Hill, Richard B. Russell and Hartwell reservoirs.