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Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV
Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nuclear evaluation, thermal and hydraulic analysis, description of tests to be performed, and discussion of containment integrity and maximum accident considerations.
Date:
March 30, 1961
Creator:
Coombe, J. R.; Brondel, J. O.; Lee, D. H. & Matthews, F. T.
System:
The UNT Digital Library
Nuclear Port Survey of the State of New York
Report of the capabilities of the state of New York to construct and service atomic propelled vessels and to handle the shipment of packaged radioactive materials, including used nuclear fuels.
Date:
November 1961
Creator:
Ebasco Services Incorporated
System:
The UNT Digital Library
Progress Report Pebble Bed Reactor Program: June 1, 1959-October 31, 1960
From abstract: This report describes analytical and development work in connection with the Pebble Bed Reactor concept. The principle involved in the reactor is the heating of graphite pebbles by the fission of contained uranium and transfer of the heat generated to helium which is circulated through the permeable bed.
Date:
July 1961
Creator:
unknown
System:
The UNT Digital Library
The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System
Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date:
December 31, 1961
Creator:
Kramer, D. & Rhodes, C. G.
System:
The UNT Digital Library
Mechanical Properties of Zircaloy-2
Abstract: The mechanical and physical properties of Zircaloy-2 were determined as a function of five test variables: temperature, grain size, direction to rolling, hydrogen content, and the presence or absence of a notch.
Date:
February 1, 1961
Creator:
Mehan, R. L. & Wiesinger, F. W.
System:
The UNT Digital Library
Mechanical Properties of Zircaloy-2 Weld Metal
Abstract: Zircaloy-2 weld metal, obtained by inert gas non-consumable-electrode welding, was subjected to tensile, strain fatigue, and creep-rupture testing.
Date:
April 15, 1961
Creator:
Beitscher, S.
System:
The UNT Digital Library
Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor
From abstract: This report describes a conceptual design and economic evaluation of 300 and 40 MWe steam-cooled fast breeder reactor power plants performed by NDA under contract with the AEC.
Date:
November 15, 1961
Creator:
Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
System:
The UNT Digital Library
Reactor Containment Design Study
Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Date:
May 18, 1961
Creator:
Johnson, R. A. & Nelson, I.
System:
The UNT Digital Library
Boiling of Freon-114 in a Three-Foot Straight Tube Evaporator
Introduction: this report covers two series of tests run on a Freon evaporator containing a vertical copper tube having an outside diameter of 7/8 of an inch, heated externally for a length of 35 inches by steam condensing in a concentric jacket.
Date:
October 19, 1961
Creator:
Allen, Charles F.
System:
The UNT Digital Library
The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
Abstract: An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres.
Date:
July 30, 1961
Creator:
Gehman, William G.
System:
The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System
Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date:
September 15, 1961
Creator:
Schlein, H.
System:
The UNT Digital Library
The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
"An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).
Date:
July 30, 1961
Creator:
Gehman, William G.
System:
The UNT Digital Library
Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor
Abstract: A conceptual reference design of a 318 Mw(e) Graphite Moderated Boiling and Superheating Reactor (GBSR) is described.
Date:
September 1961
Creator:
unknown
System:
The UNT Digital Library
Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F
Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.
Date:
February 28, 1961
Creator:
McDonald, J. S.
System:
The UNT Digital Library
Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator
Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
Date:
February 28, 1961
Creator:
Webster, L. J.
System:
The UNT Digital Library
Fabrication Modification Development for OMRE Third Core Loading
Abstract: This report describes the fabrication of elements for the OMRE third core loading.
Date:
July 15, 1961
Creator:
Peters, E. & Binstock, M. H.
System:
The UNT Digital Library
Final Safeguards Summary Report for the Piqua Nuclear Power Facility
Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date:
August 1, 1961
Creator:
unknown
System:
The UNT Digital Library
Design Modifications to the SRE during FY 1960
Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date:
February 15, 1961
Creator:
Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
System:
The UNT Digital Library
Metallurgical Aspects of SRE Fuel Element Damage Episode
Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date:
October 15, 1961
Creator:
Ballif, J. L.
System:
The UNT Digital Library
Investigations of Neutron Penetration in TiH and Steel Slabs
Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date:
May 15, 1961
Creator:
Karcher, R. H.
System:
The UNT Digital Library
Corrosion and Activity Transfer in the SRE Primary Sodium System
Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date:
October 30, 1961
Creator:
Johnson, H. E.
System:
The UNT Digital Library
Critical Path Scheduling in Maintenance
Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date:
April 10, 1961
Creator:
Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library