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Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
November 15, 1963
Creator:
Aerojet-General Corporation
Object Type:
Report
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
November 13, 1964
Creator:
Aerojet-General Corporation
Object Type:
Report
System:
The UNT Digital Library
Alpha Particle Radiolysis of Anion Exchange Resins
Technical report. From Abstract : "Irradiation of 'Dowex' 1, 'Permutit' S-1, and 'Permutit' SK anion exchange resins with alpha particles results in losses in ion exchange capacity and in 'apparent per cent crosslinkage'. The order of decreasing radiolytic stability for these properties in 'Permutit" SX > 'Permutit' S-1 > 'Dowex' 1."
Date:
November 1961
Creator:
Ahrens, Rolland W.
Object Type:
Report
System:
The UNT Digital Library
Hot-Pressure Bonding of OMR Fuel Plates
Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date:
November 15, 1959
Creator:
Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Object Type:
Report
System:
The UNT Digital Library
Some Comments on the Selection of Operating Temperatures for DPR
The results of this investigation indicate that maximum electric power generation can be obtained by selecting the turbine steam temperature within a range of plus/minus 30 degrees C. from an "idealized" steam temperature. This "idealized" steam temperature is shown to depend primarily on the maximum permissible uranium temperature. The minimum available condenser temperature and the temperature rise of the coolant in the pile effect the selection of the turbine steam temperature to lesser extent.
Date:
November 16, 1953
Creator:
Altmann, Manfred.
Object Type:
Report
System:
The UNT Digital Library
Berkeley Proton Linear Accelerator
Construction of a linear accelerator which increases the energy of protons from a 4 Mev Van de Graaff injector to a final energy of 31.5 Mev.
Date:
November 30, 1948
Creator:
Alvarez, Luis W.; Bradner, Hugh; Gordon, Hayden; Panofsky, Wolfgang K. H.; Richman, Chaim & Woodyard, John R.
Object Type:
Report
System:
The UNT Digital Library
Gas-Cooled Reactors in the USA: A Survey and Recommendation
Report that provides "an understanding of the status of gas-cooled reactors as used for unclassified applications" and determining "phases of advanced research and development needed in the field and from these to recommend a program for high-temperature, gas-cooled reactors" (p. 5).
Date:
November 1960
Creator:
Armstrong, R. H.
Object Type:
Report
System:
The UNT Digital Library
Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel
Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.
Date:
November 15, 1957
Creator:
Ashley, R. L.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Energy Deposition by Fast Neutrons. [Part] II, Yield of the Fricke Dosimeter at 14.6 Mev
A measurement of the yield of the aerated, ferrous sulfate-sulfuric acid (Fricke) dosimeter for 14.6-Mev neutrons gave a value of GF /sub Fe/sup +5/= 11.5 plus or minus 1.8. G/sub Fe/ number of ferric ions produced per 100 ev deposited. The determination combined an analysis of the energy deposit by scattering and charged particle reactions with a determination of the neutron flux by two independent means: (1) a "long counter" method and (2) an activation technique. The result is in reasonable agreement with a prediction for G/sub Fe// sup plus or minus 5/ based on measured yields of the dosimeter to irradiations by monoenergetic charged particles.
Date:
November 1963
Creator:
Axtmann, Robert C. & Licari, Joseph A.
Object Type:
Report
System:
The UNT Digital Library
Reactor Studies: Final Report, Part 1
This report presents a study investigating the possibility of designing a somewhat advanced power reactor using existing and proven technology insofar as possible. It covers a preliminary analysis of a 500 mw reactor.
Date:
November 1955
Creator:
Babcock & Wilcox Company. Atomic Energy Division.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Analysis of PM Long Life Core 3
Introduction. Under AEC contract the Martin Company has followed up the design and construction of the PM-1 and PM-3A nuclear power plants with R&D efforts seeking improved plant efficiency, increased core life and higher operating power. The Advanced PM cores have evolved step by step, with the addition of degrees of freedom to design latitude. A first replacement core, Core 2, has been designed to achieve 50 percent greater life than PM-1 through relatively minor design changes. Core 3 realizes the potential extensive modifications in the fuel element and control element configurations. This paper outlines an analysis effort undertaken to define what may be called a performance profile over a range of configurations of interest for Core 3. It should be emphasized that this is a parametric or concept study and not a final design effort. The results of this study clearly indicate that a lifetime of 100 Mw-yr can be obtained from a 7 ft pressurized water core. If employed as a 10-Mw heat source for present PM equipment, this core has a lifetime approaching that of the plant equipment, 90,000 full-power hours. Core 3 will be suitable for applications demanding up to 40-Mw operating thermal power.
Date:
November 1963
Creator:
Bagley, Raymond. & George, Critz.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Power for Pittsburgh : Final Report of Walter Kidde Nuclear Laboratories, Inc. on Duquesne-Kidde Nuclear Power Study
From foreword: The objective of this study is to determine the practical and economic use of nuclear for the production of electric power in the Pittsburgh district.
Date:
November 10, 1955
Creator:
Barker, James J.
Object Type:
Report
System:
The UNT Digital Library
Effect of Eddy Diffusion on Temperatures in a Fixed Bed, Particulate-Fueled Nuclear Reactor
Abstract: To assess diffusion's importance, the temperature distribution in a cylindrical reactor is derived for a coolant with uniform properties and velocity, taking into account both radial and axial diffusion, for a cosine-J0 power distribution. The fractional temperature rise of the coolant is found to be [chemical formula] where E(z) = [sin(z) + sin(Z)]/2 sin(Z), z= π x/2′, x is the axial distance from the core center, -H and ′ are the core half-height and extrapolated half-height, -H≤x≤H; Fn = 1/J0(Pn)·[(Pn/2.405P)2-10, J1(Pn) = 0, P= R/R′ = core radius/extrapolated radius, ρ = r/R, r = radial distance from axis, 0≤r≤R; an = = βnH/Z, 2 Aβn + 1 =[1 + 4αβ(Pn/R)2]½, A = axial diffusivity /u, B = radial diffusivity /u, u = coolant axial velocity, and [chemical formula]. The expression is evaluated for a variety of values for all the parameters, and the results are discussed analytically and presented in tables and graphs. The effect is dependent upon the relative size of the diffusion eddies in comparison with the dimensions of the reactor. The eddy diffusivity is proportional to the size of the particles in the bed and is about ten times larger axially than radially. A small core …
Date:
November 1963
Creator:
Barker, James J. & Benenati, Robert F.
Object Type:
Report
System:
The UNT Digital Library
Loop-Type Liquid-Gas Separator
The following report is a study of the separating qualities of a loop-type separator that can obtain separation with a smaller pressure drop.
Date:
November 17, 1951
Creator:
Barlow, J. W.; Jones, F. H. & Reuther, R. H.
Object Type:
Report
System:
The UNT Digital Library
Present Status of Semiconductor Particle Counters
This review lists some of the salient features of semiconductor particle counters and cannot claim to contain an exhaustive listing of all the work in the field. Performance results on the surface-barrier counters as developed at California Institute of Technology are included as typical for this type of counter, though comparable results have been obtained elsewhere.
Date:
November 23, 1959
Creator:
Barnes, C. A.
Object Type:
Report
System:
The UNT Digital Library
The Thermal Hydraulics Laboratory at Hanford
Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date:
November 1961
Creator:
Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
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
Preliminary reconnaissance of the central Zuni uplift, New Mexico
Investigating possible structural, mineralogical and volcanic relations between the central core and ore-producing sediments of the northeast flank.
Date:
November 26, 1956
Creator:
Baumgardner, Luther
Object Type:
Report
System:
The UNT Digital Library
Progress Report for the Month of November, 1947 : Contract No. AT 30-1-Gen-202
This report for November, 1947 describes progress regarding chemical work on shales and organic precipitants for uranium.
Date:
November 28, 1947
Creator:
Bearse, A. E.; Croxton, F. C. & Sullivan, John D.
Object Type:
Report
System:
The UNT Digital Library
NURE Aerial Gamma-Ray and Magnetic Reconnaissance Survey, [California]-Arizona Area, Volume 1 - Narrative Report: Salton Sea (NI 11-9), Phoenix (NI 12- 7), El Centro (NI 11-12), Ajo (NI 12-10), Lukeville (NH 12-1) Quadrangles
From abstract "As part of the Department of Energy (DoE) National Uranium Resource Evaluation Program, LKB Resources, Inc. has performed a rotary-wing reconnaissance high sensitivity radiometric and magnetic survey, encompassing several 1:250,000 quadrangles in southwestern Arizona and southeastern California. The surveyed area consisted of approximately 9300 line miles. The radiometric data was corrected and normalized to 400 feet terrain clearance. The data was identified as to rock type by correlating the data samples with existing geologic maps. Statistics defining the mean and standard deviation of each rock type are presented as listings in Volume I of this report. The departure of the data from its corresponding mean rock type is computed in terms of standard deviation units and is presented graphically as anomaly maps in Volume II and as computer listings in microfiche form in Volume I."
Date:
November 1979
Creator:
Bendix Field Engineering Corporation. Grand Junction Operations.
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
SM-1 Research and Development Program: Long-lived Induced Activity Buildup During SM-1 Core I Lifetime. Task XVIII, Phase I
Abstract: The results of activity buildup studies in the SM-1 performed during Core I lifetime (June 3, 1957 to April 28, 1960) are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Radiation levels after reactor shutdown are presented, as well as mathematical equations used to account for the observed activity levels. The data have shown that Co60 is the major contributor to radiation levels in the SM-1. Co60 activity arises from the cobalt in Haynes 25 alloy flux suppressors, and the cobalt impurity in stainless steel. After 35 months operation at an average power level of 55%, deposited Co60 activity accounted for approximately 83% of the total radiation level (mr/hr) contributed by the long-lived gamma emitting nuclides. The contribution of the primary coolant activity to the total radiation level is insignificant when compared to the contribution of the activity deposited on the walls of the system. The radiation level on the super-heater side of the steam generator was about 1400 mr/hr after 35 months of reactor operation. The percentages of Co60 activity in the coolant and in the deposits were not the same. This indicates …
Date:
November 30, 1960
Creator:
Bergmann, C. A.; Bergen, C.; Cox, J. F.; Chupak, J. & Grant, L. G.
Object Type:
Report
System:
The UNT Digital Library
Effect of Fluoride Ions on the Aqueous Corrosion of Zirconium Alloys
Abstract. A review has been made of the effects of fluoride ions on the corrosion behavior of zirconium alloys in high-temperature water. Corrosion was found to occur as the result of contamination of the water or the zirconium surface. A major source of fluorides is undue delay in rinsing the HF-HNO3 pickling solution during surface preparation. The oxide on corrosion-resistant material has been found to contain up to 7600 ppm fluoride from this source. The threshold concentration of fluoride in the oxide film which produces poor corrosion resistance ranges from 8500 to 17,000 ppm. Accelerated corrosion from fluorides in water at 300 to 360 C occurs at about 100 ppm, although increased corrosion has been reported at 10 ppm fluoride in water at 300 C. Fluorocarbon plastics degrade and contribute fluorides to the high-temperature water or to the alloy surface when in direct contact with zirconium. Chlorides (1 to 10,000 ppm) and iodides (1270 ppm) do not adversely affect the corrosion behavior of zirconium alloys in water at 360 C. The mechanism of corrosion is not well understood but apparently is related to the formation of insoluble zirconium oxyfluorides during pickling and during exposure to fluoride-contaminated water.
Date:
November 1963
Creator:
Berry, Warren E., 1922-
Object Type:
Report
System:
The UNT Digital Library