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Final project report, June 1, 1957-January 31, 1981

Description: Research at the University of Colorado cyclotron from June 1, 1957 through January 31, 1981 is summarized. Facility programs included cyclotron design, engineering and construction, negative hydrogen ion acceleration, the beam swinger, detector development, plasma physics of the ion source, and computing. Experimental areas during the period included reaction mechanism studies, isobaric analog states and the Lane model, multinucleon transfer, nuclear astrophysics, pre-equilibrium reaction mechanism studies, nuclear spectroscopy, and two-proton pairing studies. Research was also carried out in intermediate energy physics and nuclear theory. A list of publications is included. (GHT)
Date: April 1, 1981
Creator: Peterson, R.J.
Partner: UNT Libraries Government Documents Department

Waste Management Plan for the Drilling Within the Chromium Plume West of 100-D/DR Reactors

Description: This waste management plan provides guidance for managing drilling spoils generated during the installation of groundwater wells in the 100-D/DR Area, which is part of the 100-HR-3 Operable Unit. The wells are being installed to meet two objectives: (1) better define the nature and extent of a previously identified chromium plume in the area, and (2) act as groundwater extraction wells if the contamination warrants
Date: December 31, 1997
Creator: Peterson, R.E.
Partner: UNT Libraries Government Documents Department

Approximation of continuity of lenticular Mesaverde Group sandstone lenses utilizing close-well correlations, Piceance Basin, NW Colorado. SPE 11610

Description: Mesaverde Group sandstone units in 13 closely-spaced wells in the central and southern Piceance Basin of Colorado were correlated utilizing wireline log response quantitatively and qualitatively. Based on these correlations, the environmental subdivisions of the Mesaverde Group were characterized as follows: (1) paralic (upper mixed-marine) zone, occurring in the uppermost Mesaverde Group, includes thick sandstone units which are interpreted to be regionally continuous, (2) fluvial zone, containing point-bars 20 to 30+ ft thick, is interpreted to be correlatable to a maximum of 6800 ft, and (3) paludal zone has insufficient data to adequately characterize the sand units. However, 63 percent of the units are correlatable across at least 139 ft. An approximation of the dimensional characteristics of Mesaverde sandstone units has potential applications in designing hydraulic fracturing treatments and estimating gas reserves more accurately. 15 figures, 2 tables.
Date: January 1, 1982
Creator: Peterson, R.E. & Kohout, J.B.
Partner: UNT Libraries Government Documents Department

Hydrogen Release from Simulated Sludge and Saltcake

Description: This report describes the results of the Savannah River Technology Center (SRTC) program to address bubble gas release potential as requested by Concentration, Storage and Transfer Engineering. Researchers from the Waste Processing Technology Section (WPTS) and Immobilization Technology Section (ITS) contributed to the results presented.
Date: January 5, 1999
Creator: Peterson, R.A.
Partner: UNT Libraries Government Documents Department

Idealized mixing impacts

Description: The dispersion of tetraphenylborate in continuous stirred tank reactors plays a significant role in the utility achieved from the tetraphenylborate. Investigating idealized mixing of the materials can illuminate how this dispersion occurs.
Date: December 8, 1999
Creator: Peterson, R.A.
Partner: UNT Libraries Government Documents Department

Solvent Extraction External Radiation Stability Testing

Description: Personnel irradiated a number of samples of calixarene-based solvent. Analysis of these samples indicated that measurable loss of the calixarene occurred at very high doses (-16 Mrad). No measurable loss of the Cs-7SB modifier occurred at equivalent doses. The primary degradation product, 4-sec-butylphenol, observed during analysis of the samples came from degradation of the modifier. Also, TOA proved more susceptible to damage than the other components of the solvent. The total degradation of the solvent proved relatively minor. The consistent solvent performance, as indicated by the measured D Cs values, after exposure at high total doses serves as evidence of the relatively low degree of degradation of the solvent components. Additional tests employing internal irradiation of solvents with both simulants and SRS tank waste will be completed by the end of March 2001 to provide confirmation of the results presented herein.
Date: January 5, 2001
Creator: Peterson, R.A.
Partner: UNT Libraries Government Documents Department

Open grid vs mesh grid as the extraction field structure in a streak camera image-converter tube

Description: It is concluded that the dynamic range of a streak tube does not depend on whether it uses a fine-mesh or an open structure to provide the extraction field. An RCA C-73435 streak tube body was fitted with two extraction grid structures by replacing the conventional open grid with a steel plate containing two apertures. One aperture simulated the open grid structure; the other was a 2 x 20 mm slit covered with a fine mesh (40 wires per mm, 38% transmissive). The apertures were equal distances above and below the tube axis. Using 35-ps pulses, dynamic range curves were taken at 1.06 ..mu..m on one aperture at a time, while blocking the other aperture. As we anticipated, the tube saturated at nearly the same point for the open and mesh apertures. The noise levels for both apertures were almost equal and very close to the film fog level. Noise level was lower than for earlier measurements on other makes of tubes with a fine-mesh grid. The dynamic range for both apertures was in the order of 6000, which indicates that the lower dynamic range of other tubes must be due to something other than the use of a fine-mesh grid.
Date: May 13, 1982
Creator: Thomas, S.W. & Peterson, R.L.
Partner: UNT Libraries Government Documents Department

Recondensation of vaporized material in the Cascade ICF reactor

Description: In the Cascade inertial fusion reactor, the innermost blanket zone consists of solid granules of C or BeO. The x rays from a fusion pulse of 300 MJ will vaporize up to 1 kg of material. The temperature of this vaporized material may reach 1 to 2 electron volts. The CONRAD code was used to calculate the energy and mass exchange between this hot plasma and the cold wall until complete recondensation of the material reduces the chamber particle density to 3 x 10 V cm T, which is required for propagation of the next laser pulse. Our calculations indicate that recondensation times are in the few to tens of milliseconds range even if only the first layer of granules is available for recondensation. Gas flow calculations indicate that several layers of granules should be available for recondensation. We discuss phenomenology, not currently in the CONRAD model, that could lead to increased recondensation times. 17 refs., 5 figs.
Date: November 15, 1985
Creator: Hogan, W.J. & Peterson, R.R.
Partner: UNT Libraries Government Documents Department

Development of ultrasonic methods for examining stainless steel welds. Interim progress report

Description: Spurious ultrasonic (UT) signals obtained during the examination of austenitic stainless steel welds in LMFBR components have emphasized the need to develop more effective UT methods to supplement the examination processes presently employed during fabrication, and for use during subsequent in-service inspection of LMFBR plants. This interim report documents the first year's effort on a program that was designed to investigate this problem and develop viable solutions. Sixty-eight weld samples were acquired, cataloged, and subjected to a series of ultrasonic, radiographic, and metallographic examination procedures. It was determined that although spurious UT noise signals could usually be associated with major dendritic grain growth patterns, the existence and magnitude of some of the observed noise signals could not be explained simply on the basis of dendritic microstructure. The results obtained during application of a series of ultrasonic and radiographic characterization procedures are included, in addition to photomicrographs and photomicrographic montages taken in the vicinity of numerous sites which produced ultrasonic noise signals of various amplitudes. A concurrent investigation was conducted to evaluate the performance of conventional ultrasonic examination procedures. These results are compared with the laboratory investigation results, and a brief outline of future work planned under this program is presented. (auth)
Date: November 1, 1975
Creator: Peterson, R.O.; Spanner, J.C. & Mech, S.J.
Partner: UNT Libraries Government Documents Department

Neutron radiographic facility at the 3-mw Livermore pool-type reactor

Description: A description is presented of the neutron experimental radiographic facility at the Livermore Pool-Type Reactor. This facility was installed in 1974 to assist Lawrence Livermore Laboratory research programs. Some of the testing techniques used to modify the neutron beam and the present radiographic parameters are also discussed. (auth)
Date: September 10, 1975
Creator: Richards, W.J.; Peterson, R.T. & Prindle, J.A.
Partner: UNT Libraries Government Documents Department

Decomposition Studies of Triphenylboron, Diphenylborinic Acid and Phenylboric Acid in Aqueous Alkaline Solutions Containing Copper

Description: This report documents the copper-catalyzed chemical kinetics of triphenylboron, diphenylborinic acid and phenylboric acid (3PB, 2PB and PBA) in aqueous alkaline solution contained in carbon-steel vessels between 40 and 70 degrees C.
Date: February 11, 1997
Creator: Crawford, C.L. & Peterson, R. A.
Partner: UNT Libraries Government Documents Department

Costs and impacts of transporting nuclear waste to candidate repository sites

Description: In this paper, a status report on the current estimated costs and impacts of transporting high-level nuclear wastes to candidate disposal sites is given. Impacts in this analysis are measured in terms of risk to public health and safety. Since it is difficult to project the status of the nuclear industry to the time of repository operation - 20 to 50 years in the future - particular emphasis in the paper is placed on the evaluation of uncertainties. The first part of this paper briefly describes the characteristics of the waste that must be transported to a high-level waste disposal site. This discussion is followed by a section describing the characteristics of the waste transport system. Subsequent sections describe the costs and risk assessments of waste transport. Finally, in a concluding section, the effect of the uncertainties in the definition of the waste disposal system on cost and risk levels is evaluated. This last section also provides some perspectives on the magnitude of the cost and risk levels relative to other comparable costs and risks generally encountered. 13 references, 2 figures, 16 tables.
Date: December 31, 1983
Creator: McSweeney, T.I.; Peterson, R.W. & Gupta, R.
Partner: UNT Libraries Government Documents Department