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Nuclear Safety Program Annual Progress Report: for Period Ending December 31, 1968
Report containing material from several Oak Ridge National Laboratory groups regarding nuclear safety.
Date:
June 1969
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Irradiation behavior of unalloyed hypostoichiometric uranium carbide, experiment AI 3-11 and review
A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review
Date:
June 22, 1968
Creator:
Frank, J. E.; Forrester, R. E. & Buck, J. S.
System:
The UNT Digital Library
Irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
A report regarding irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12
Date:
June 22, 1968
Creator:
Arnold, J. L.
System:
The UNT Digital Library
High heat flux heater development status report
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 is described.
Date:
June 15, 1968
Creator:
McKisson, R. L. & Babbe, E. L.
System:
The UNT Digital Library
Instrumentation and Controls Division Annual Progress Report for the Period Ending September 1, 1966
Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Instrumentation and Controls Division during 1966. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date:
June 1967
Creator:
Borkowski, C. J.; Dandl, R. A.; Epler, E. P. & Harrill, C. S.
System:
The UNT Digital Library
Reactor Development Program Progress Report: May 1966
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date:
June 30, 1966
Creator:
Adams, R. M. & Glassner, A.
System:
The UNT Digital Library
UNICORN: a program to calculate point cross sections from resonance parameters
A report regarding Unicorn - a program used to calculate point cross-sections from resonance parameters.
Date:
June 30, 1966
Creator:
Otter, J. M.
System:
The UNT Digital Library
Gamma-Ray Spectrometry of Neutron-Deficient Isotopes: Annual Progress Report, June 1966
Progress report discussing the activities in "a program of studies of nutron-deficient nuclides using the techniques of gamma-ray spectroscopy" (abstract).
Date:
June 1966
Creator:
Heath, R. L. & Cline, J. E.
System:
The UNT Digital Library
Calandria Core Weld Joint Development
Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.
Date:
June 30, 1965
Creator:
Roberts, J. G.
System:
The UNT Digital Library
A Rotary Kiln for the Controlled Oxidation of UC
Abstract: A rotary kiln was evaluated for the controlled oxidations of UC.
Date:
June 30, 1965
Creator:
Strausberg, S.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 1964
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
Creator:
unknown
System:
The UNT Digital Library
SNAP 10A FSEM-3 Agena Compatibility Test
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.
System:
The UNT Digital Library
Spark-Source Mass Spectrometric Analysis of Common and Radiogenic Lead
Analysis that is fast and has extremely low levels of detection for more than forty elements that may be present in lead.
Date:
June 11, 1965
Creator:
Franklin, John C. & Griffin, E. B.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1965
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date:
June 1965
Creator:
Trauger, D. B. & Whitman, G. D.
System:
The UNT Digital Library
Liquid MHD Power Cycle Studies
Report issued by the Argonne National Laboratory discussing the magnetohydrodynamics (MHD) power cycle for liquid metals. The benefits, and different phases of the MHD power cycle are presented. This report includes tables, and illustrations.
Date:
June 1965
Creator:
Petrick, Michael & Lee, Kung-You
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
Date:
June 1965
Creator:
Briggs, R. B.
System:
The UNT Digital Library
Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel
The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.
Date:
June 1965
Creator:
Fletcher, R. D.
System:
The UNT Digital Library
STEP Project Quarterly Technical Report: January-June 1964
Report regarding the Safety Test Engineering Program (STEP), the transient and destructive testing of the aerospace SNAP 10A/2 reactor, and the evaluation of the results of these tests.
Date:
June 1965
Creator:
U.S. Atomic Energy Commission. Idaho Operations Office.
System:
The UNT Digital Library
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops
Report issued by the Oak Ridge National Laboratory discussing natural-circulation corrosion test loops. As stated in the abstract, "an investigation was undertaken to determine the compatibility of conventional nickel, iron, and cobalt-base high-temperature alloys with boiling potassium. The tests were designed to obtain quantitative information on the dissolution of the container alloys by condensing potassium and the subsequent deposition of solute in the subcooled liquid region of the test device" (p. 1). This report includes tables, illustrations, and illustrations.
Date:
June 1965
Creator:
Jansen, D. H. & Hoffman, E. E.
System:
The UNT Digital Library
Thin Wall Tubing Tests Using Ultrasonic Shear Waves: Part 2 - Production Test Equipment, Its Operation and Test Results
Report describing Hanford Laboratories' second report regarding thin wall tubing tests. This part covers "the production [of] test equipment developed, its operation, and test results" (p. 2).
Date:
June 30, 1964
Creator:
Zeutschel, M. F. & Dixon, N. E.
System:
The UNT Digital Library
Analog Models for HNPF Control and Protection Studies
Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.
Date:
June 15, 1964
Creator:
Dunsmore, C. L.
System:
The UNT Digital Library
HNPF Control System Response During Transient Conditions
Abstract: This report documents the results of power ramps inposed on the HNPF during the month of January 1964.
Date:
June 15, 1964
Creator:
Shaw, P. F.
System:
The UNT Digital Library
Operating Experience with Heat Transfer System Pumps at the Hallum Nuclear Power Facility
Introduction: It is the purpose of this report to describe the operating and maintenance experience obtained at HNPF on the sodium heat transfer pumps.
Date:
June 15, 1964
Creator:
Durand, R. E.
System:
The UNT Digital Library
Electronuclear Research Division Annual Progress Report, December 31, 1963
Report containing ongoing research and development taking place at the Oak Ridge National Laboratory's Electronuclear Division.
Date:
June 1964
Creator:
Oak Ridge National Laboratory. Electronuclear Research Division.
System:
The UNT Digital Library