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Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office
Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date:
April 1, 1958
Creator:
ACF Industries Incorporated. Nuclear Products - ERCO Division.
Object Type:
Report
System:
The UNT Digital Library
Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office
Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date:
April 1, 1958
Creator:
ACF Industries Incorporated. Nuclear Products - ERCO Division.
Object Type:
Report
System:
The UNT Digital Library
Scale "Up or Down" Analysis for Prototype Test
Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date:
May 1, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Semi-Annual Progress Report in Chemistry for the Period October 1,1950--March 31,1951
Report discussing the progress made on various chemistry research projects at Ames Laboratory during the period from October 1, 1950 to March 31, 1951.
Date:
May 1, 1951
Creator:
Ames Laboratory
Object Type:
Report
System:
The UNT Digital Library
Occurrence of Technetium in Nature : Final Report for the Period November 1, 1954 to August 31, 1955
Twelve neutron activation analyses for naturally occurring technetium-98 were performed. Positive results were obtained in ten cases. Precautions were taken to avoid interference by molybdenum and technetium-99. the cross section for the reaction [formula] as found to be equal to 4 +- 2 mb for the neutron spectrum of the vertical thimbles of the Argonne CP-5 reactor. The chemical state of molybdenum (VI) in basic solution was studied by an anion-exchange technique. Evidence was obtained for the existence of polymeric species at pH-values up to 14. Preliminary work on the stability of Domax-1 anion exchange resin in perchlorate media indicates rapid deterioration even at 0.2F ClO4-.
Date:
September 1, 1955
Creator:
Anders, Edward, 1926-
Object Type:
Report
System:
The UNT Digital Library
Halogen Collector Test Program
Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date:
March 1, 1960
Creator:
Arthur D. Little, Inc.
Object Type:
Report
System:
The UNT Digital Library
Description of Developmental Fast Neutron Breeder Power Reactor Plant
Report that generally describes sodium cooled fast reactors, the features and facilities of such a reactor proposed by Atomic Power Development Associates, and then its safety and siting considerations.
Date:
September 1, 1955
Creator:
Atomic Power Development Associates
Object Type:
Report
System:
The UNT Digital Library
A Study of the Carrier Distillation Excitation of Iron in U3O8
Abstract: "A radioactive tracer, Fe^59, was used to determine the disposition of iron as a result of the excitation of a U3O8 matrix in a d - c arc. Two different spectrographic procedures, both using carrier distillation excitation techniques, were compared as to the percent of iron volatilized, the percent of iron diffused into the electrode and the percent of iron remaining in the residual charge."
Date:
October 1, 1957
Creator:
Atwell, M. G. & Pepper, C. E.
Object Type:
Report
System:
The UNT Digital Library
Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE
Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
Date:
June 1, 1960
Creator:
Ballif, J. L.; Hayward, B. R. & Walter, J. W.
Object Type:
Report
System:
The UNT Digital Library
A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures
Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date:
July 1, 1951
Creator:
Bareis, D. W.
Object Type:
Report
System:
The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service
Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date:
May 1, 1960
Creator:
Baroczy, C. J.
Object Type:
Report
System:
The UNT Digital Library
Engineering Study of Evaporation for Concentrating Radioactive Liquid Wastes : Engineering Research Final Report
Summary: "The problem of evaporation of secondary radioactive wastes resulting from waste disposal studies at Mound Laboratoy has been studied experimentally to determine the fundamental design characteristics of a plant size unit. Emphasis, of course, was on decontamination, but the factors affecting foaming and scaling also had to be investigated and evaluated. Generally speaking, the final design is a standard type of evaporator, the only unique feature being the relation of the two effects. Where critical, as affecting performance, the particular design features have been specified."
Date:
November 1, 1950
Creator:
Bates, R. L. & McEwen, M.
Object Type:
Report
System:
The UNT Digital Library
The Elimination of Microwave Reflections
Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."
Date:
February 1, 1955
Creator:
Beard, David
Object Type:
Report
System:
The UNT Digital Library
A Discussion on the Layout of Elements of a Control Panel
This memorandum is an outline of the principles and methods employed by 5100 Human Engineering Personnel in consultation on test equipment panel layout. The process of control panel layout is partially formalized with particular emphasis on test equipment panels. An experimental method is proposed for selecting an optimum panel layout. The essential role of experimentation is pointed out. The optimal layout for a nonrepetitive procedure is deduced and generalized to give methods of layout solution for the general repetitive procedure.
Date:
August 1, 1955
Creator:
Beeler, J. R.
Object Type:
Report
System:
The UNT Digital Library
Electrodecontamination of Stainless Steel
Abstract: "In experimental studies, decontamination factors of 1000 to 3000 were obtained by electrostripping deposited radioactivity from stainless steel surfaces, used as the anode, in 2% sulfuric acid at current densities as low as 0.01 amp/in.-2. Stainless steel cathodes were used. The method was successfully applied to contaminated equipment."
Date:
November 1, 1954
Creator:
Bennett, M. R.
Object Type:
Report
System:
The UNT Digital Library
Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program
Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report.
Date:
March 1, 1965
Creator:
Blevitt, R.; Paine, G. & Sudar, S.
Object Type:
Report
System:
The UNT Digital Library
A Survey of Non-Fuel-Bearing Materials for the Marine Gas-Cooled Reactor
Results of an initial examination of non-fuel-bearing materials for the Marine Gas Cooled Reactor are presented. Areas given specific attention include structural and cladding materials and graphite moderator. Other areas not included because of classification include zirconium hydride moderator and control materials. In each report section, available pertinent information is summarized and a plan for future work is given.
Date:
May 1, 1958
Creator:
Bokros, J. C.; Dijkstra, L; & Merten, U.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Foreign Multiplier Phototubes
"Several multiplier phototubes produced by England, Russia, or Switzerland were evaluated for amplification, photocathode sensitivity, photo-electron collection efficiency, cathode uniformity, and dark current. A description of the various tubes by designation numbers is given, along nth a description of techniques and equipment used in testing."
Date:
January 1, 1958
Creator:
Bolakas, J. & Parker, P G.
Object Type:
Report
System:
The UNT Digital Library
The Development and Operation of the NRTS Laundry
Equipment lists and operating procedures are present for a laundry designed to wash contaminated clothing.
Date:
December 1, 1955
Creator:
Bonnett, John R.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Reactor Project Progress Report, January 1948
This report is a progress report detailing operations and ongoing projects at the Brookhaven National Laboratory. The report describes new developments with buildings and progress regarding ongoing experiments. The report includes photographs showing progress in the construction of the reactor and other images and figures that accompany the descriptions of projects.
Date:
January 1, 1948
Creator:
Borst, L. B. & Fox, Marvin
Object Type:
Report
System:
The UNT Digital Library
Measurement of the Behavior of a Plasma in a Magnetic Field by Means of Probes
Abstract: "Probes were used to measure certain properties of the cloud of positive ions and electrons ejected from a pulsed ion source having two hydrogen-loaded electrodes. Time-of-flight measurements show: the presence of H+ ions with 50 ev directed energy; an increase of this energy with increasing pulse current in the source; a higher peak yield of ions with higher peak currents in the source; and higher yields and higher ion energies up to 110 ev have been recorded with the use of a pulsed magnetic field impressed upon the source. The neutral positive ion-electron beam from the source has been projected against an increasing magnetic field and the reflected and transmitted signals have been recorded and compared as a function of the magnetic field. Probe signals from the plasma as it encounters the magnetic field are oscillatory, suggesting that magnetohydrodynamic phenomena are presented."
Date:
December 1, 1954
Creator:
Bostick, W. H.; Zizzo, S. G. & Cook, Buford
Object Type:
Report
System:
The UNT Digital Library
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)
Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
Date:
February 1, 1965
Creator:
Botts, W. V.; Marko, M.; McCourt, P. E.; Keshishian, V.; Piccot, A. R. & Budney, G. S.
Object Type:
Report
System:
The UNT Digital Library
The Use and Calibration of Scintillation Counter--Model Y
Several improvements have been made in the gamma scintillation counter (GSC). The Model V gamma scintillation counter uses a canned thallium activated sodium iodide crystal as a detector. Although the electronic components remain unchanged, a modification of the sample support has been made to improve reproducibility of geometry. To assure comparable results between various counters, they must be operated at the same energy threshold and counting yield. Methods have been developed to assure operation at a preferred energy threshold of 0.1 Mev and an arbitrarily fixed counting yield of 3.36% for Cs-Ba-137. Partial pulse height discrimination against U 237 is also accomplished.
Date:
August 1, 1953
Creator:
Brauer, F. P. & Leboeuf, M. B.
Object Type:
Report
System:
The UNT Digital Library
High Frequency Induction Heating
Abstract: Equations are given to calculate at least approximately the heating in solid and hollow cylinders, slabs and spheres. Short and long cylinders are treated as well as short and long solenoids. The complicated mathematics used to derive the equations given will be omitted as they may be found in the original references. Heating with a spark gap converter is covered. Equations are given which together with some experimental data should enable the reader to predict the efficiency, heating, or temperature to be expected as the charge or coil is changed. Units and conversion factors are mentioned briefly.
Date:
February 1, 1947
Creator:
Bromley, LeRoy A.
Object Type:
Report
System:
The UNT Digital Library