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30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System
Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Date:
January 31, 1962
Creator:
Alco Products (Firm)
System:
The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location
Report describing a the design requirements of a proposed nuclear power plant for use on an ice cap.
Date:
January 15, 1959
Creator:
Alco Products (Firm)
System:
The UNT Digital Library
A Miniature Mixer Settler
Unit developed at Knolls Atomic Power Laboratory for extraction and overcomes the disadvantages of the batch countercurrent units currently in use.
Date:
January 5, 1956
Creator:
Alter, H. Ward; Coplan, B. V. & Zebroski, E. L.
System:
The UNT Digital Library
Chromosomal Aberrations in a Natural Population of Chironomus Tentans Exposed to Chronic Low-Level Environmental Radiation
From introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."
Date:
January 29, 1964
Creator:
Blaylock, B. Gordon; Auerbach, S. I. & Nelson, D. J.
System:
The UNT Digital Library
Electronic Analog Computer Study of a Nuclear Reactor Steam Pressurizer
Study consists of setting up the computer on the situation representing test vessel and setting up the full size pressurizer vessel on the analog computer.
Date:
January 20, 1956
Creator:
Bremer, J. W.
System:
The UNT Digital Library
Radiological Aspects of SNAPTRAN 2/10A-3 Destructive Test
From abstract: "This report describes in detail an extensive monitoring grid used to monitor the radiological effects of the destructive excursion and subsequent release of fission products."
Date:
January 1965
Creator:
Cordes, O. L.; Bird, R. P.; Dinneen, G. A. & Fielding, J. R.
System:
The UNT Digital Library
Advanced Test Reactor Burnout Heat Transfer Tests
From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Date:
January 1964
Creator:
Croft, M. W.
System:
The UNT Digital Library
Safeguard Report: Livermore Pool Type Reactor
Safety measures of the Livermore Pool Type Reactor in reaction to certain meteorological conditions and following the improbable rupture of the reactor building.
Date:
January 17, 1957
Creator:
Detterman, Robert L.
System:
The UNT Digital Library
Fast Neutron Data
A report concerning fast neutrons including theory and compiled data.
Date:
January 25, 1950
Creator:
Feshbach, H.
System:
The UNT Digital Library
Design Study: Sodium Modular Reactor
This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date:
January 15, 1960
Creator:
General Electric Company
System:
The UNT Digital Library
Liquid Metal Fast Breeder Reactor Design Study: Volume 1
From abstract: "A detailed description of a reference 1000-MWe fast breeder reactor plant is presented, together with design specifications and the experimental bases for the design."
Date:
January 1964
Creator:
General Electric Company
System:
The UNT Digital Library
Liquid Metal Fast Breeder Reactor Design Study: Volume 2
From introduction: "Documentation of the various considerations and design techniques involved in the design of the reference 1000-MWe fast oxide breeder reactor."
Date:
January 1964
Creator:
General Electric Company
System:
The UNT Digital Library
INDEX: a Computer Program for Indexing X-ray Diffraction Powder Patterns
From introduction: "...a logical system has been developed to yield rapidly the indexing of a given powder pattern by using an electronic computer."
Date:
January 1965
Creator:
Goebel, J. B. & Wilson, Archie Spencer
System:
The UNT Digital Library
Scintillation Hand and Foot Counter
From abstract: "The design of a scintillation counter for measuring radioactive contamination of hands and feet is described."
Date:
January 27, 1953
Creator:
Goldsworthy, William
System:
The UNT Digital Library
Evaluation of Diethers as Uranium Extractants
Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.
Date:
January 14, 1963
Creator:
Googin, J. M.; Harper, W. L.; Phillips, L. R. & Postma, Fred W.
System:
The UNT Digital Library
High Power Density Development Project: Interim Report, 300 MWe HPD Conceptual Design Study
From introduction: "Preliminary design and analysis of the 300 MWe core."
Date:
January 5, 1962
Creator:
Grayhek, V. G.
System:
The UNT Digital Library
Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants
Abstract: This technical report covers the investigation of 17-4 PH steel components used in the SM-1, SM-1A and PM-2A nuclear power plants, which consist of control rod drive racks, pinions, seal shafts and associated parts. Evidence supporting the continued use of 17-4 PH steel in these applications is presented. Alco's current procurement and processing specifications for 17-4 PH steel are included. The evidence presented is in the form of stress calculations, test and environmental data and the results of non-destructive and destructive metallographic analyses.
Date:
January 23, 1962
Creator:
Haraway, E. S. & Saccocio, R. M.
System:
The UNT Digital Library
Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation
From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
Date:
January 23, 1963
Creator:
Hartzfeld, H. A. & Regier, R. B.
System:
The UNT Digital Library
High Power Density Development Project: Third Quarterly Progress Report, October - December, 1960
From introduction: "Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC."
Date:
January 1, 1961
Creator:
Holland, L. K.
System:
The UNT Digital Library
Ultrasonic Resin Level Detector
This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date:
January 15, 1960
Creator:
Hunter, D. O. & Pleasance, C. L.
System:
The UNT Digital Library
Experiments and Analysis for SM-1 Core II With Special Components
Abstract: This technical report contains a summary of analytical and experimental work performed on SM-1 Core II, with special components is presented. The effects of these special assemblies upon power distribution and core reactivity were calculated and compared to experimental measurements. A thermal analysis was conducted to determine steady state and transient performance of the special test components of the core as well as some of the hotter standard Core II components. Experimental work discussed includes individual reactivity effects of all the special elements and the total effect of all of the elements. Power mappings were also made and are reported.
Date:
January 1, 1961
Creator:
Lee, D. H.; Robinson, R. A. & Segalman, I.
System:
The UNT Digital Library
Conversion of UNH to UO3 : Terminal Report
Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.
Date:
January 10, 1951
Creator:
Maness, R. F. & Clagett, F.
System:
The UNT Digital Library
Graphical Representation of the Four Series of Isotopes
Three graphs representing the four series of isotopes.
Date:
January 18, 1949
Creator:
Morgan, K. Z.; Patterson, V. K. & Western, F.
System:
The UNT Digital Library
SM-1 Reactor Core Inspection at 2/3 Core Life : March 7, 1959 to May 17, 1959
Abstract: This technical report is concerned with the program and results of the SM-1 reactor vessel head removal and core inspection at Fort Belvoir, Virginia from the period March 7, 1969 to May 17, 1959. It covers the operating procedures in detail and records the conditions found and problems encountered in order to make a record for reference in future work of this nature. The major objective of the program, to obtain irradiation data on the SM-1 type core, has been met. The boron control rod elements were found unsatisfactory for full core life, and europium oxide elements were placed in the core for future irradiation stability data. A major problem was experienced with the cracked pressure vessel head studs. The methods developed for the removal of the broken studs are presented. The complete metallurgical study of the stud failure from stress corrosion is included as Appendix B.
Date:
January 13, 1960
Creator:
Obrist, C. H.; Byrne, B. J.; Connolly, T. F.; Foley, D. D.; Lichtenberger, R. V.; Mackay, S. D. et al.
System:
The UNT Digital Library