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Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1961 - December 1, 1961
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:
December 30, 1961
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
Shipboard Cobalt-60 Radiopasteurizer for Marine Products
Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
Date:
June 30, 1963
Creator:
Manowitz, B.; Kuhl, A. O.; Galanter, L.; Armel, J.; Black, K. M.; Klaassen, W. J. et al.
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
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes
Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date:
July 30, 1963
Creator:
Pessl, H. J.
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
Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant
From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date:
September 30, 1959
Creator:
Linenberger, G. A.
System:
The UNT Digital Library
Metallurgy Division Annual Progress Report, July 1, 1960
Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date:
September 30, 1960
Creator:
Oak Ridge National Laboratory. Metallurgy Division.
System:
The UNT Digital Library
A Neutron Absorption Alignment Chart
From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
Date:
July 30, 1957
Creator:
Nisle, Robert G.
System:
The UNT Digital Library
EDP Procedures in Technical Library Operations
Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date:
July 30, 1963
Creator:
Griffin, Hillis L.
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
P-V-T Relationships of BF₃ Gas
Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.
Date:
July 30, 1960
Creator:
Smith, C. R. F.
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
Valve Stem Freeze Seal for High-Temperature Sodium
Abstract: An experimental study of valve stem freeze seals was undertaken as part of the effort to develop components for high temperature service in advanced sodium-cooled reactor systems.
Date:
July 30, 1960
Creator:
McDonald, J. S.
System:
The UNT Digital Library
OMR (Piqua) Unitized Control-Safety Rod Prototype Tests
Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).
Date:
June 30, 1960
Creator:
Howell, J. D. & Weeks, C. C.
System:
The UNT Digital Library
High Temperature Corrosion of Some Metals and Ceramics in Fluorinating Atmospheres
Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.
Date:
September 30, 1960
Creator:
Hale, C. F.; Barber, E. J.; Bernhardt, H. A. & Rapp, Karl E.
System:
The UNT Digital Library
SRE Fuel Element Damage: An Interim Report
Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date:
November 30, 1959
Creator:
Jarrett, A. A.
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
Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant
From abstract: A preliminary study has been made of a direct access, streamlined process for the rapid fabrication of fuel using uranium-233.
Date:
July 30, 1962
Creator:
Nowak, W. B. & Wessling, B. W.
System:
The UNT Digital Library
Design Evaluation and Comparison 200 MWe Boiling D₂O Pressure Tube Indirect and Direct Cycle Power Reactor Plants
From foreword: This report is concerned with the investigation of an indirect cycle plant which was the subject of a joint study between Sargent & Lundy and NDA.
Date:
June 30, 1960
Creator:
unknown
System:
The UNT Digital Library
Boiling Songs and Associated Mechanical Vibrations
From introduction: The study is based entirely on observations which have been made at a number of different installations at which boiling songs and vibrations were noted during heat transfer experiments.
Date:
June 30, 1960
Creator:
Firstenberg, H.
System:
The UNT Digital Library
A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal
From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date:
November 30, 1962
Creator:
unknown
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 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
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