Ions from EBIS are injected into Booster after acceleration by an RFQ and a Linac. The velocity of the ions at Booster injection is c{beta} where c is the velocity of light and (1) {beta} = 0.0655. The kinetic energy is (2) W = mc{sup 2}({gamma}-1) where m is the ion mass and (3) {gamma} = (1-{beta}{sup 2}){sup -1/2}. Putting in numbers one gets a kinetic energy of approximately 2 MeV per nucleon for each ion. The revolution period at injection is 10.276 {micro}s. The ions in the EBIS trap are delivered in a beam pulse that ranges from 10 to 40 {micro}s in length. This amounts to 1 to 4 turns around the machine. The transverse emittance (un-normalized) of EBIS beams just prior to injection into Booster is 11{pi} mm milliradians in both planes. This is an order of magnitude larger than the nominal 1{pi} mm milliradians for Tandem beams. Injection proceeds by means of an electrostatic inflector in the C3 straight section and four programmable injection dipoles in the C1, C3, C7, and D1 straights. These devices have been in use for many years for the injection of ions from Tandem as described in [1] and [2]. The …

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This report describes the existing and proposed methodologies for performing measurements of contamination prior to releasing material for uncontrolled use at the Hanford Site. The technical basis for the proposed methodology, a modification to the existing contamination survey protocol, is also described. The modified methodology, which includes a large-area swipe followed by a statistical survey, can be used to survey material that is unlikely to be contaminated for release to controlled and uncontrolled areas. The material evaluation procedure that is used to determine the likelihood of contamination is also described.

This report contains geologic, geochemical, and physical characterization data collected on sediment recovered from boreholes C4104 and C4105 in the T Tank Farm, and 299-W-11-39 installed northeast of the T Tank Farm. The measurements on sediments from borehole C4104 are compared to a nearby borehole 299-W10-196 placed through the plume from the 1973 T-106 tank leak. This report also presents the data in the context of sediment types, the vertical extent of contamination, the migration potential of the contaminants, and the likely source of the contamination in the vadose zone and groundwater below the T Tank Farm. Sediment samples were characterized for: moisture content, gamma-emission radionuclides, one-to-one water extracts (which provide soil pH, electrical conductivity, cation, trace metal, radionuclide and anion data), total carbon and inorganic carbon content, and 8 M nitric acid extracts (which provide a measure of the total leachable sediment content of contaminants). Overall, our analyses showed that common ion exchange is a key mechanism that influences the distribution of contaminants within that portion of the vadose zone affected by tank liquor. We observed slight elevated pH values in samples from borehole C4104. The sediments from the three boreholes, C4104, C4105, and 299-W10-196 do show that sodium-, …

One of the hallmarks of linear coupling is the resonant exchange of oscillation amplitude between the horizontal and vertical planes when the difference between the unperturbed tunes is close to an integer. The standard derivation of this phenomenon (known as the difference resonance) can be found, for example, in the classic papers of Guignard [1, 2]. One starts with an uncoupled lattice and adds a linear perturbation that couples the two planes. The equations of motion are expressed in hamiltonian form. As the difference between the unperturbed tunes approaches an integer, one finds that the perturbing terms in the hamiltonian can be divided into terms that oscillate slowly and ones that oscillate rapidly. The rapidly oscillating terms are discarded or transformed to higher order with an appropriate canonical transformation. The resulting approximate hamiltonian gives equations of motion that clearly exhibit the exchange of oscillation amplitude between the two planes. If, instead of the hamiltonian, one is given the four-by-four matrix for one turn around a synchrotron, then one has the complete solution for the turn-by-turn (TBT) motion. However, the conditions for the phenomenon of amplitude exchange are not obvious from a casual inspection of the matrix. These conditions and those …

Ten closely spaced, shallow (<100 ft) drill cores were obtained from the 1.22-Ma-old Bandelier Tuff at a 4-acre site for proposed construction at Los Alamos National Laboratory, New Mexico. The goal of the investigation was to identify faults that may have potential for earthquake-induced surface ruptures at the site. Careful mapping of contact surfaces within the Bandelier Tuff was supplemented with results of geochemical analyses to establish unit boundaries with a high degree of accuracy. Analysis shows that the upper contact surface of Unit 3 of the Bandelier Tuff provides no evidence of faults beneath the building site, and that the subsurface structure is consistent with a shallowly dipping (< 2{degree}), unbroken block. Because no significant or cumulative faulting events have disturbed the site in the last 1.22 million years, it is unlikely that surface rupture will occur at the site in future large earthquakes. Uncertainty analysis suggests that this method would detect faults with {ge}2 ft of cumulative stratigraphic separation.

The feasibility of using the KEWB reactor as a pulsed neutron radiation source for use in studies of fuel element transient heating was studied. UC fuel rod samples were heated in the reactor. It was found that flux distribution in fuel samples could be mapped and thermal conductivity measurements for UC could be made by using fast response thermocouples distributed radially in the sample. (J. R.D.)

Tungsten in uranium--tungsten alloys is determined by precipitating the tungsten from a cold sulfuric acid solution using alpha -benzoinoxime and cinchonine as the precipitating agents. The precipitate is dgnited at 800 deg C and weighed as WO/sub 3/. Results of 94 determinations on known samples containing 20 to 40 milligrams of tungsten in the presence of 1 to 8 grams of uranium showed an average recovery of 100.1% with a standard deviation of 0.7%. (auth)

A report is made on the Kinetic Experiment on Water Beller Program. The purpose of this program is to examine the dynamic behavior of homogeneous research reactors to obtain the information necessary for the evaluation of the nuclear safety of such reactors. Step inputs of reactivity were systematically increased and the first test core, a spherical core designed for stable power operation at 50 kw, was examined under conditions of 4% reactivity release This is the maximum normally installed in such reactors A 4% reactivity release places the reactor on a 2 millisecond stable period and leads to a peak power of 530 Mw. This represents the fastest intentional power excursion of any thermal reactor. The reactivity released is more than twice that which any other has withstood without damage. The maximum pressure in the system for this transient was a sharp pressure peak of 370 psia. This pressure is well below that required to cause yield of a typical water boller core. (A.C.)

This report provides a proposed residual contamination guide (RCG) for the 324 Building B-Cell Cleanout Project, Phase 1, at the Hanford Site. The RCG is expressed as a fraction of the amount of highly dispersible radioactive material that would result in offsite doses equal to the Pacific Northwest Laboratory radiological risk guidelines following the worst credible accident scenario for release of the holdup material. The proposed RCG is 10{sup {minus}1} to 10{sup {minus}2} of the PNL radiological risk guidelines. As part of the development of the RCG, a number of factors were considered. These include the need to provide an appropriate level of flexibility for other activities within the 324 Building that could contribute to the facility`s overall radiological risk, uncertainties inherent in safety analyses, and the possible contribution of other 300 Area facilities to overall radiological risk. Because of these factors and the nature of the cleanout project, the RCG is expressed as a range rather than a point value. This report also provides guidance on determining conformance to the RCG, including inspection and measurement techniques, quality assurance requirements, and consideration of uncertainty.

Total hydrocarbon production in the Michigan Basin has surpassed 1 billion barrels (Bbbls) and total unrecovered reserves are estimated at 1--2 BBbls. However, hydrocarbon production in Michigan has fallen from 35 MMbbls/yr in 1979 to about 10 MMbbls/yr in 1996. In an effort to slow this decline, a field demonstration project designed around using a horizontal well to recover bypassed oil was designed and carried out at Crystal Field in Montcalm County, MI. The project had two goals: to test the viability of using horizontal wells to recover bypassed oil from the Dundee Formation, and to characterize additional Dundee reservoirs (29) that are look alikes to the Crystal Field. As much as 85 percent of the oil known to exist in the Dundee Formation in the Michigan Basin remains in the ground as bypassed oil. Early production techniques in the 137 fields were poor, and the Dundee was at risk of being abandoned, leaving millions of barrels of oil behind. Crystal Field in Montcalm County, Michigan is a good example of a worn out field. Crystal Field was once a prolific producer which had been reduced to a handful of wells, the best of which produced only 5 barrels per …

This Index provides a description of all wind summaries available at the National Climatic Center.

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Data collected during studies of Onslow Bay, off the North Carolina coast during cruises during September, 1975, are reported. Current meters and thermography were placed at depths of 10 and 22 m along the 28 m isobath in the northeastern and southwestern sectors of the Bay. Data are included on wind turbulence and velocity; seawater salinity and temperature at various depths; the content of nitrates, phosphates, silicate, oxygen, chlorophyll, and phytoplankton biomass at various depths. Hydrographic and meteorologic conditions during the cruises are included. (CH)

A computational method to determine cross-section requirements quantitatively is described and applied to the Tokamak Fusion Test Reactor (TFTR). In order to provide a rational basis for the priorities assigned to new cross- section measurements or evaluations, this method includes quantitative estimates of the uncertainty of currently available data, the sensitivity of important nuclear design parameters to selected cross sections, and the accuracy desired in predicting nuclear design parameters. Perturbation theory is used to combine estimated cross-section uncertainties with calculated sensitivities to determine the variance of any nuclear design parameter of interest. (auth)

This document describes the geology and hydrogeology at the former Advanced Coal Liquefaction Research and Development (ACLR&D) facility in Wilsonville, Alabama. The work was conducted by personnel from the Oak Ridge National Laboratory Grand Junction office (ORNL/GJ) for the U.S. Department of Energy (DOE) Pittsburgh Energy Technology Center (PETC). Characterization information was requested by PETC to provide baseline environmental information for use in evaluating needs and in subsequent decision-making for further actions associated with the closeout of facility operations. The hydrogeologic conceptual model presented in this report provides significant insight regarding the potential for contaminant migration from the ACLR&D facility and may be useful during other characterization work in the region. The ACLR&D facility is no longer operational and has been dismantled. The site was characterized in three phases: the first two phases were an environmental assessment study and a sod sampling study (APCO 1991) and the third phase the hydraulic assessment. Currently, a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remedial investigation (RI) to address the presence of contaminants on the site is underway and will be documented in an RI report. This technical memorandum addresses the hydrogeologic model only.

This report is the first in the series of bibliographies supporting the efforts at the Brookhaven National Laboratory ALARA Center on dose reduction at DOE facilities. Abstracts for this bibliography were selected from proceedings of technical meetings, journals, research reports, and searches of the DOE Energy Data Base. The abstracts included in this report relate to operational health physics as well as other subjects which have a bearing on dose reduction. Facilities covered include: radioactive waste, uranium enrichment, fabrication, unirradiated fissile materials storage, irradiated fissile material storage, reprocessing, decommissioning, recovery, hot laboratories, tritium production, reactors (research, test and production but not power reactors), and accelerators. We have also included material in improved design, materials selection, planning, and other topics which are related to dose-reduction efforts. The report contains 68 abstracts as well as subject and author indices.

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This report documents information collected by the Pacific Northwest Laboratory {sup (a)} at the request of Westinghouse Hanford Company. Presented in this report is the interpretation of the hydrogeologic environment at the 2101-M Pond, located in the 200-East Area of the Hanford Site. This information and its accompanying interpretation were derived from sampling and testing activities associated with the installation of four ground-water monitoring wells, in addition to data gathered from several previously existing wells. The new monitoring wells were installed as part of a groundwater monitoring program initiated in 1988. The four new monitoring wells were installed around the 2101-M Pond between May 23 and August 27, 1988. Geologic sampling, aquifer testing, and initial ground-water sampling were performed during the installation of these wells. Laboratory analyses of the sediment samples for particle size, calcium carbonate content, and selected natural and contaminant constituents were performed. A full year of quarterly ground-water sampling and the first statistical analysis of background and downgradient data have also been performed. 112 refs., 49 figs., 18 tabs.

Using a two-dimensional algorithm, steering of triode slots was investigated for the first time with a reasonable accounting of the ion extraction sheath.

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