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Aerial Radiometric and Magnetic Survey Tularosa National Topographic Map, New Mexico: Volume 1

Description: From Operational Program: This final report includes a general geologic description of the area, including descriptions of the various geologic units and correlates the airborne data to the geologic units as provided by the geologic maps. Also included is a frequency distribution study of the data as a function of the geologic units encountered over the NTMS area including the tie line data.
Date: December 15, 1978
Creator: United States. Department of Energy. Grand Junction Office.
Location: See Bounding Coordinates
Partner: UNT Libraries Government Documents Department
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Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Green Bay NTMS Quadrangle, Wisconsin

Description: From abstract: Results of a reconnaissance geochemical survey of the Green Bay Quadrangle, Wisconsin are reported. Field and laboratory data are presented for 695 groundwater samples, 546 stream sediment samples, and 401 stream water samples. Statistical and areal distributions of uranium and other possibly uranium-related variables are displayed. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential fo… more
Date: June 15, 1978
Creator: National Uranium Resource Evaluation Program
Partner: UNT Libraries Government Documents Department
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Evaluation of Uranium Potential in Selected Pennsylvanian and Permian Units and Igneous Rocks in Southwestern and Southern Oklahoma: Final Report

Description: Introduction: The areas of study include parts of the Wichita uplift, Arbuckle uplift, Hunton-Pauls Valley uplift, Central Oklahoma platform, Muenster-Waurika arch, and Anadarko basin (Fig. 1.1-1). Rocks examined include the Precambrian granite of the Arbuckle uplift, Cambrian igneous rocks of the Wichita uplift, and Pennsylvanian-Permian sedimentary rocks derived in large part from those two uplifts and, to a lesser extent, from the Ouachita system.
Date: June 15, 1977
Creator: Al-Shaieb, Zuhair; Shelton, John W.; Donovan, R. Nowell; Hanson, Richard E. & May, Richard T.
Partner: UNT Libraries Government Documents Department
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High Heat Flux Heater Development Status Report

Description: Report describing the development of a high heat flux heater for use in corrosion rate and stress-rupture tests of fuel cladding materials in a sodium environment.
Date: June 15, 1968
Creator: McKisson, R. L. & Babbe, E. L.
Partner: UNT Libraries Government Documents Department
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SRE-PEP Moderator Elements: Final Report

Description: Report discussing the design and engineering of the new Zircaoloy-2 moderator and reflector elements for the Solid Reactor Experiment (SRE) Power Expansion Program (PEP). The existing design, proposed design, and details of the final design are described. Additional aspects described include are material properties, thermal analysis, stress analysis, and the final proof test.
Date: January 15, 1966
Creator: Jones, C. E.
Partner: UNT Libraries Government Documents Department
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Carbide Fuels in Fast Reactors

Description: Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: June 15, 1965
Partner: UNT Libraries Government Documents Department
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SNAP 10A FSEM-3 Agena Compatibility Test

Description: From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.
Date: June 15, 1965
Creator: Teresa, M.
Partner: UNT Libraries Government Documents Department
open access

A Sequence for Predicting Waste Transport by Ground Water

Description: From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
Partner: UNT Libraries Government Documents Department
open access

The HASL Surface Air Sampling Program Summary Report For 1963

Description: Report that summarizes the first year of the Surface Air Sampling Program, including the results of analyzing 1,700 air filter samples and 400 precipitation samples.
Date: January 15, 1965
Creator: Volchok, Herbert L. (Herbert Lee), 1926-1987
Partner: UNT Libraries Government Documents Department
open access

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 1964

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: December 15, 1964
Creator: Cole, H. S.; Hausknecht, D. F.; Jenkins, O. G., Jr.; Lew, D. E.; Mandel, H.; Pearson, E. N. et al.
Partner: UNT Libraries Government Documents Department
open access

Analysis of Stresses in Bellows

Description: Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
Partner: UNT Libraries Government Documents Department
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Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses

Description: Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.
Date: October 15, 1964
Creator: Lurie, H. & Noyes, R. C.
Partner: UNT Libraries Government Documents Department
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Construction Completion Report: CAI-816, 100-N Reactor Plant

Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
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Criticality-Accident Dosimetry Studies

Description: Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date: October 15, 1964
Creator: Bailey, J. C.
Partner: UNT Libraries Government Documents Department
open access

Design of an Experimental Bowable Fuel Element for the SRE

Description: Abstract: An experimental bowable fuel element was developed to study temperature oscillations in the second core loading of the SRE.
Date: October 15, 1964
Creator: Peckinpaugh, C. L.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Coolant Impurity Removal Equipment at the OMRE

Description: Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Partner: UNT Libraries Government Documents Department
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