Serial/Series Title
108 Matching Results
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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
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
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
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
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
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
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
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
Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors
This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.
Date:
March 1, 1962
Creator:
Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L.
System:
The UNT Digital Library
Multi-Channel Boiling Stability for Sodium Graphite Reactors
Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
Date:
March 1, 1962
Creator:
Cappel, H. H.
System:
The UNT Digital Library
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code
Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date:
April 15, 1962
Creator:
Baller, D. C.
System:
The UNT Digital Library
Thermal Stress Testing of Beryllium Oxide Moderator Shapes
Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
Date:
August 1, 1962
Creator:
Sujata, H. L.; King, M. & Waters, F. J.
System:
The UNT Digital Library
Capsule Irradiation of Unalloyed Uranium at High Temperatures
Abstract: Cast and Wrought specimens and restrained wrought specimens of unalloyed uranium were irradiated in the Materials Testing Reactor, as the first in a series of experiments to develop fuel materials for sodium cooled reactors.
Date:
August 15, 1962
Creator:
Harrington, D. G. & Newton, J. B.
System:
The UNT Digital Library
Environmental Monitoring Semiannual Report: January-June 1962
From summary: This report summarizes environmental monitoring results for the first six months of 1962.
Date:
November 1962
Creator:
Moore, J. D.; Fisher, W. L. & Rowe, P. A.
System:
The UNT Digital Library
Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits
Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date:
February 1, 1963
Creator:
Holland, J. W.
System:
The UNT Digital Library
Dynamic Void Fraction Measurement System
Abstract: Various methods and techniques of measuring void fractions in boiling heat transfer media are discussed.
Date:
May 15, 1963
Creator:
Kendron, J. H.; Stoner, E. E. & Taylor, G. M.
System:
The UNT Digital Library
Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices
Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.
Date:
June 30, 1963
Creator:
Campbell, R. W.; Doyas, R. J.; Field, H. C.; Guderjahn, C. A.; Guenther, R. L.; Hausknecht, D. F. et al.
System:
The UNT Digital Library
Boiling Studies for Sodium Reactor Safety: Part 1, Experimental Apparatus and Results of Initial Tests and Analysis
Abstract: An experimental and analytical research program is described which is designed to meet certain specific needs for data and methods required to make improved predictions of transient voids, burnout, flow, and fuel temperature during extreme accidents in sodium-cooled reactors.
Date:
August 30, 1963
Creator:
Noyes, R. C.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963
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:
November 30, 1963
Creator:
Auleta, J. J.
System:
The UNT Digital Library
Inpile Experiments on Retention of Fission Products in 500°F Sodium
Abstract: The results of three separate inpile capsule experiments are presented.
Date:
January 30, 1964
Creator:
Kunkel, W. P.; Elliot, D. M. & Gibson, A. S.
System:
The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963
From summary: The full 140 element loading of the core was completed on October 10, 1962. At this point, critical operation was begun for operator training and post-critical testing purposes.
Date:
March 1, 1964
Creator:
Darley, D. K.
System:
The UNT Digital Library
QUICKIE: A Computer Program for Spatially Independent Multigroup Slowing-Down and Thermalization Calculations
Introduction: QUICKIE is a computer program designed to solve the multigroup neutron slowing down and thermalization equations without consideration of spatial dimensions.
Date:
April 15, 1964
Creator:
Boling, M. & Rhoades, W.
System:
The UNT Digital Library
SNAP 2: Structural and Dynamic Analysis
Abstract: The structural design criteria and the system basic loads for the SNAP 2 compact power unit are presented.
Date:
May 1, 1964
Creator:
Castle, R. A.
System:
The UNT Digital Library
Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System
Abstract: Pressure-temperature isochores were obtained for zirconium-hydrogen alloys, spanning the H/Zr composition range of 1.430 to 1.910. The studies were confined to the temperature limits of 300 to 900ºC, and the pressure limits of 0.01 to 10.0 atm.
Date:
May 31, 1964
Creator:
Raymond, J. W.
System:
The UNT Digital Library