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Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969
Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
Date:
October 1969
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1969
From summary: "Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory."
Date:
October 1969
Creator:
Oak Ridge National Laboratory. Health Physics Division.
System:
The UNT Digital Library
Reactor Development Program Progress Report: September 1966
Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date:
October 26, 1966
Creator:
Adams, R. M. & Glassner, A.
System:
The UNT Digital Library
Analysis of Stresses in Bellows
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.
System:
The UNT Digital Library
Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses
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.
System:
The UNT Digital Library
Construction Completion Report: CAI-816, 100-N Reactor Plant
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.
System:
The UNT Digital Library
Criticality-Accident Dosimetry Studies
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.
System:
The UNT Digital Library
Design of an Experimental Bowable Fuel Element for the SRE
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.
System:
The UNT Digital Library
Evaluation of Coolant Impurity Removal Equipment at the OMRE
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.
System:
The UNT Digital Library
Radiolysis Products of Polyphenyl Coolants: Part 3, Omre High Boilers
Abstract: The nature of the high boiling radiolysis products of OMRE coolants was studied extensively.
Date:
October 15, 1964
Creator:
Keen, R. T.; Orr, W. L.; Miller, L. J.; Sullivan, R. J. & Shepard, R. C.
System:
The UNT Digital Library
Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
Discussion of laboratory tests to reduce uranium corrosion.
Date:
October 14, 1964
Creator:
Sprague, T. P.; Googin, J. M. & Phillips, L. R.
System:
The UNT Digital Library
Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications
Abstract: Under the Power Expansion Program (PEP), modifications have been made to the Sodium Reactor Experiment (SRE) facility to improve plant reliability and permit an increase in power to 30 Mwt, with a reactor coolant outlet temperature up to 1200°F.
Date:
October 9, 1964
Creator:
Freede, W. J. & Roberts, J. K.
System:
The UNT Digital Library
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs.
Date:
October 1964
Creator:
Wilhelm, Donald J.
System:
The UNT Digital Library
The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel
Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2).
Date:
October 1964
Creator:
Silker, W. B. & Thomas, C. W.
System:
The UNT Digital Library
An Engineering Test Program to Investigate a Loss of Coolant Accident
From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
Date:
October 1964
Creator:
Wilson, T. R.; Hauge, O. M.; Matheney, G. B. & Homer, G. B.
System:
The UNT Digital Library
The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1
Report regarding an experimental program by Hanford Laboratories' in order "to determine the long-term irradiation behavior of the graphite used as the moderator in N-Reactor. The primary objectives of the program are to provide data for predictions of the distortion of the N-Reactor moderator and the stress conditions which could arise from the difference in the the rate and extent of contraction between the transverse and parallel orientations of the graphite bars" (p. 1).
Date:
October 1964
Creator:
Helm, J. W.
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1964 - September 1, 1964
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
October 1, 1964
Creator:
Hardy, Edward P., Jr. & Rivera, Joseph
System:
The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements
Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Date:
October 1964
Creator:
Swanberg, F.
System:
The UNT Digital Library
Solid State Division Annual Progress Report, May 31, 1964
Report containing ongoing research and development of the Solid State Division of the Oak Ridge National Laboratory.
Date:
October 1964
Creator:
Oak Ridge National Laboratory. Solid State Division.
System:
The UNT Digital Library
Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride
Report issued by the Oak Ridge National Laboratory discussing thermodynamic calculations of nuclear fuels. As stated in the introduction, "the equations developed in this report could be used to calculate the capacity of chlorine for transporting plutonium tetrachloride" (p. 2). This report includes tables, and illustrations.
Date:
October 1964
Creator:
Gens, T. A.
System:
The UNT Digital Library
Ultramicro Methods in Biochemistry: [Part] 3. The Determination of Serum Cholesterol, [Part] 4. The Determination of Glucose
From Introduction: "The following report details the development of an ultra-micro method for the determination of serum cholesterol."
Date:
October 1964
Creator:
Van Stewart, E. & Longwell, Bernard B.
System:
The UNT Digital Library
Zirconium Processing Capability of the Idaho Chemical Processing Plant
Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
Date:
October 1964
Creator:
Bower, J. R.
System:
The UNT Digital Library
Feed Materials Production Center Summary Technical Report: July 1, 1963-September 30, 1963
From abstract: The temperature of molten uranium was measured indirectly by an infrared radiation pyrometer. The emissivities of graphite and molten uranium were determined, and a series of equations correlating pyrometer readings with melt temperatures was derived.
Date:
October 28, 1963
Creator:
unknown
System:
The UNT Digital Library
A Photographic Study of Boiling Flow
From abstract: A high speed motion picture study was conducted of boiling flow in a vertical, rectangular channel at atmospheric pressure. Three different visual flow regimes were defined and described.
Date:
October 25, 1963
Creator:
Vohr, John Henry
System:
The UNT Digital Library