224-UA continuous calciner trough examination (open access)

224-UA continuous calciner trough examination

The continuous calciners at UO{sub 3} Plant are of a new design which was developed at HAPO and placed in service late in 1956. The heat transfer troughs are considered to be the most vulnerable parts of the calciners because of their high operating temperatures. Thermal stresses are calculated to be quite high, and when added to the direct mechanical stresses from powder load etc., come close to the limiting safe stress for stainless steel at the operating temperature. It is felt that trough failure will be progressive as a result of creep type distortion and cracks at stress concentration points. The higher the stress (and temperature), the more rapid the rate of failure will be. All possible steps have been taken to limit maximum trough temperature, rate of change, and variations from one part of the trough to another. These steps were not always successful and various troughs have been subjected to rather severe temperature shocks as well as high mechanical stresses due to agitator failures. Despite these difficulties, no signs of failure could be detected by visual inspection. It was decided, therefore, that a more complete examination should be made. This examination was made to determine the present …
Date: March 10, 1958
Creator: Kennedy, R. A.
Object Type: Report
System: The UNT Digital Library
Accidental Dispersion of Reactor Poisons and the Controlled Distance Required (open access)

Accidental Dispersion of Reactor Poisons and the Controlled Distance Required

Two types of hypothetical reactor catastrophe are considered. In the first of these, the Boiling Accident,'' it is assumed that a fraction of the radioactive material in a reactor is released to the atmosphere at a steady rate over a period of hours. In the second, the Puff Accident,'' it is assumed that the release of the radioactive material takes place instantaneously.'' The following concepts are used as measures of the hazard existing outside the controlled plant area. Danger Distance,'' defined as that distance beyond which the fission product cloud becomes so dilute that it cannot cause death; Probabiiity of Death per Capita per Accident,'' which is a measure of the hazard to any individual; and Expectation Number of Deaths per Accident.'' which is a statistical measure of the hazard to the entire off-site populace. Three mechanisms for each type of catastrophe were considered: direct irradiation from the fission product cloud, inhalation of the air in the cloud, and rainout from the cloud followed by irradiation from the ground. Failout is not considered. for it requires that a very energetic explosion be assumed. It is concluded that the size of the plant should be set by the hazard of irradiation …
Date: March 1, 1958
Creator: Menegus, R. L. & Ring, H. F.
Object Type: Report
System: The UNT Digital Library
An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept (open access)

An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept

From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Date: March 1, 1958
Creator: Hanford Works
Object Type: Report
System: The UNT Digital Library
An Advanced Engineering Test Reactor (open access)

An Advanced Engineering Test Reactor

A concpept for an advanced enineering test reactor is described. Thpe results of various investigations with regard to alternative design possibilitipes are presented. Retailed information is given rearding the nuclear and enineering calculations. (W.D.M.)
Date: March 15, 1958
Creator: Leyse, C. F.; Bertelson, P. C.; Chmielewski, W. S.; Delicate, W. S.; Francis, T. L.; Kornfeld, M. J. et al.
Object Type: Report
System: The UNT Digital Library
Aerodynamic and inlet-flow-field characteristics at a free-stream Mach number of 3.0 for airplanes with circular fuselage cross sections and for two engine locations (open access)

Aerodynamic and inlet-flow-field characteristics at a free-stream Mach number of 3.0 for airplanes with circular fuselage cross sections and for two engine locations

Report presenting an experimental investigation of several airplane configurations at Mach 3.0 in a continuous flow tunnel. The configurations had circular fuselage cross sections and a sweptback wing and either two nacelles or two side inlets.
Date: March 18, 1958
Creator: Dryer, Murray & Luidens, Roger W.
Object Type: Report
System: The UNT Digital Library
Aerodynamic characteristics of a canard and an outboard-tail airplane model at a Mach number of 2.01 (open access)

Aerodynamic characteristics of a canard and an outboard-tail airplane model at a Mach number of 2.01

From Introduction: "In order to obtain some insight into the relative merits of canard and outboard-tail control systems at supersonic speeds, a preliminary investigation of a generalized canard and outboard-tail model has been conducted in the Langley 4- by 4-foot supersonic pressure tunnel at a Mach number of 2.01 and the results are presented herein."
Date: March 24, 1958
Creator: Spearman, M. Leroy & Robinson, Ross B.
Object Type: Report
System: The UNT Digital Library
An Analog Study of the Influence of Internal Modifications to a Wing Leading Edge on Its Transient Temperature Rise During Highspeed Flight (open access)

An Analog Study of the Influence of Internal Modifications to a Wing Leading Edge on Its Transient Temperature Rise During Highspeed Flight

Memorandum presenting an investigation made with an electrical heat-flow analog to determine the effect of internal modifications to a wing leading edge on the surface-temperature rise and temperature distribution for conditions of transient aerodynamic heating at high supersonic speeds. Results regarding the leading-edge temperature rise, influence of conduction on leading-edge temperature for skins of uniform thickness, and surface-temperature distribution are provided.
Date: March 17, 1958
Creator: Neel, Carr B.
Object Type: Report
System: The UNT Digital Library
Analysis of stresses and deflections in a disk subjected to gyroscopic forces (open access)

Analysis of stresses and deflections in a disk subjected to gyroscopic forces

From Summary: "Results are presented in dimensionless form suitable for design purposes. The method for solving the problem of a disk of variable thickness with a temperature gradient is also presented."
Date: March 1958
Creator: Hirschberg, M. H. & Mendelson, A.
Object Type: Report
System: The UNT Digital Library
An Analysis of the Optimization of a Beam Rider Missile System (open access)

An Analysis of the Optimization of a Beam Rider Missile System

"The paper begins with a discussion of the optimum system and the corresponding minimum error. A brief discussion of this miss as a function of the parameters which determine it is then given" (p. 2).
Date: March 1958
Creator: Shinbrot, Marvin & Carpenter, Grace C.
Object Type: Report
System: The UNT Digital Library
Analysis of two-stage counterrotating turbine efficiencies in terms of work and speed requirements (open access)

Analysis of two-stage counterrotating turbine efficiencies in terms of work and speed requirements

From Introduction: "This report represents an extension of the material presented in reference 4 to the case of the counterrotating turbine where the inter-stage stator is omitted and the second-stage rotor blade velocity is in the direction opposite to that of the first-stage rotor."
Date: March 18, 1958
Creator: Wintucky, William T. & Stewart, Warner L.
Object Type: Report
System: The UNT Digital Library
Annual Report of the Boy Scouts of America: 1957 (open access)

Annual Report of the Boy Scouts of America: 1957

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1957, activities, organizational leadership, and other information about scouting programs.
Date: March 12, 1958
Creator: Boy Scouts of America
Object Type: Report
System: The Portal to Texas History
Appendix to Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office (open access)

Appendix to Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office

Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS).
Date: March 1958
Creator: U.S. Atomic Energy Commission. Idaho Operations Office.
Object Type: Report
System: The UNT Digital Library
Application of a high-temperature static strain gage to the measurement of thermal stresses in a turbine stator vane (open access)

Application of a high-temperature static strain gage to the measurement of thermal stresses in a turbine stator vane

From Introduction: "This report describes the high-temperature static strain gage and presents the results obtained in a determination of the thermal stresses in a turbine stator vane resulting from the temperature distribution obtained under steady-state conditions at rated speed and temperature of the engine."
Date: March 1958
Creator: Kemp, R. H.; Morse, C. R. & Hirschberg, M. H.
Object Type: Report
System: The UNT Digital Library
The Application of a Nominal 48 WT % U-Al Alloy to Plate-type Aluminum Research Reactor Fuel Elements (open access)

The Application of a Nominal 48 WT % U-Al Alloy to Plate-type Aluminum Research Reactor Fuel Elements

Under the Atoms-For-Peace Plan, the specification that uranium be limited to 20% enrichment in the U/sup 236/ isotope has necessitated development of a highly-concentrated uranium--aluminum alloy as the fuel material in the composite aluminum plates of research reactor fuel elements. Efforts have been directed to determining the suitability of a nominal 48 wt.% U--Al alloy in relation to previously established procedures for manufacturing platetype aluminum fuel elements. Increasing the uranium concentration from 18 wt. % to the 48 wt.% resulted in increased segregation, higher strength, and loss of ductility, creating additional fabrication difficulties. Nonuniform deformation of the alloy during roll bonding into composite plates caused localized thinning of the cladding which may limit the material to specific reactor applications. Substitution of Type 6061 aluminum for Type 1100 alumium as frame and cladding of the fuel plates improves this condition. A fuel element, containing the 48 wt.% U-Al alloy, was irradiated in the active lattice of the MTR to an estimated burnup of 25% of the U/sup 235/ atoms with no observable damage. (auth)
Date: March 11, 1958
Creator: Thurber, W. C.; Erwin, J. H. & Beaver, R. J.
Object Type: Report
System: The UNT Digital Library
Approximations for the thermodynamic and transport properties of high-temperature air (open access)

Approximations for the thermodynamic and transport properties of high-temperature air

Report presenting the thermodynamic and transport properties of high-temperature air in closed form starting from approximate partition functions for the major components in air and neglecting all minor components. The compressibility, energy, entropy, specific heats, speed of sound, coefficients of viscosity and thermal conductivity, and Prandtl numbers for air are provided for a range of temperatures and pressures.
Date: March 1958
Creator: Hansen, C. Frederick
Object Type: Report
System: The UNT Digital Library
Beef-cattle breeds for beef and for beef and milk. (open access)

Beef-cattle breeds for beef and for beef and milk.

Presents brief descriptions of the breeds of cattle which are kept for beef or for both beef and milk in the United States.
Date: March 1958
Creator: Clark, R. T. (Richard Turnbull), 1902-1965
Object Type: Book
System: The UNT Digital Library
A BIBLIOGRAPHIC FILE OF TECHNICAL REPORT ABSTRACTS USEFUL TO REACTOR CONTROL SYSTEM ENGINEERING (open access)

A BIBLIOGRAPHIC FILE OF TECHNICAL REPORT ABSTRACTS USEFUL TO REACTOR CONTROL SYSTEM ENGINEERING

Report abstracts from more than 40 AEC and foreign facilities, AE C contractors, and technical periodicals are represented, published throughout the years 1941 to 1958. Cards for current publications are placed in the file no later than six weeks after the abstracts appear in the Abstracts of Classified Reports. (auth)
Date: March 1, 1958
Creator: Green, F P
Object Type: Report
System: The UNT Digital Library
BIOLOGICAL AND MEDICAL RESEARCH DIVISION SEMIANNUAL REPORT FOR JULY THROUGH DECEMBER 1957 (open access)

BIOLOGICAL AND MEDICAL RESEARCH DIVISION SEMIANNUAL REPORT FOR JULY THROUGH DECEMBER 1957

affecting the production of antibodies in irradiated rabbits; the effects of irradiation on the serological activity of ovalbumin; factors affecting the growth of transplanted mouse ascites carcinomas in rats; the effects of strontium-90 on the life span and incidence of bone tumors in mice; the effects of irradiation on xanthine concentration and xanthine oxidase activity in chicken liver homogeaates; the stability under various biochemical conditions and hydrolysis of S-adenosylmethionine; the biosynthesis and use as a growth factor substitute of S-adenosylmethionine by yeast mutants; design modifications of the Coulter counter, designed for red blood cells, for use in counting and sizing bacteria; electron microscope observations on fibrillogenesis in the regenerating achilles tendon of normal, scorbutic, and recovering guinea pigs; the response of mice to conditioning doses of whole-body gamma irradiation; the incidence of thymic lymphomas in mice exposed to low-dose daily cobalt-60 gamma irradiation; the relative effectiveness of cobalt-60 gamma rays and fission neutrons for producing duodenal damage in mice; genetic factors affecting tail spotting in mice; the effect of deuterium oxide on kidney function in rats; the influence of the endocrine glands on radioinduced hyperpigmentation in mice; the protective effects of injected bone marrow against radiation injuries in mice; the …
Date: March 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Borax-IV Reactor: Manufacture of Fuel and Blanket Elements (open access)

Borax-IV Reactor: Manufacture of Fuel and Blanket Elements

The procedures used in fabricating the core loading for the natural water-cooled Borax-IV reactor are described. Manufacturing of the fuel plates and blanket plates, which contain fissile (U/sup 235/) and/or fertile (Th/sup 232/) material in ceramic form, lead-bonded within tubes in aluminum-1 wi.% nickel extrusions, is described in deteil. A brief description of the assembly and welding of the finished plates into subassemblies and assemblies is given. Preparation of the ceramic bodies was described by others in ANL-5669 and ANL- 5678. (auth)
Date: March 1, 1958
Creator: Walker, D. E.; Noland, R. A.; McCuaig, F. D. & Stone, C. C.
Object Type: Report
System: The UNT Digital Library
Calculation of Flutter Characteristics for Finite-Span Swept or Unswept Wings at Subsonic and Supersonic Speeds by a Modified Strip Analysis (open access)

Calculation of Flutter Characteristics for Finite-Span Swept or Unswept Wings at Subsonic and Supersonic Speeds by a Modified Strip Analysis

Report presenting a method for calculating flutter characteristics of finite-span swept or unswept wings at subsonic and supersonic speeds. Flutter characteristics were calculated using this method for 12 wings of varying sweep angle, aspect ratio, taper ratio, and center-of-gravity position at a range of Mach numbers.
Date: March 18, 1958
Creator: Yates, E. Carson, Jr.
Object Type: Report
System: The UNT Digital Library
CHEMICAL EQUILIBRIA AND REACTION RATES FOR HYDROFLUORINATION OF UO$sub 2$ FROM "AMMONIUM DIURANATE" AND FROM UO$sub 3$ (open access)

CHEMICAL EQUILIBRIA AND REACTION RATES FOR HYDROFLUORINATION OF UO$sub 2$ FROM "AMMONIUM DIURANATE" AND FROM UO$sub 3$

Reaction rates for the hydrofluorination of UO/sub 2/ derived from two widely different source materials (sulfated pot-denitrated UO/sub 3/ and "ammonium diuranate," (ADU)) were determined in a thermobalance over a wide range of temperatures (460 deg F to 1150 deg F) and with several HF--H/sub 2/O gas phase mixtures varying from 20 to 100 per cent HF. These data were then organized to yield single plots for each type of feed material. From these plots, maximum instantaneous reaction rates may be determined. These values may be applied to problems dealing with the estimation of minimum retention times required for hydrofluorination in counter-current gas-solid contactors. In addition to the rate studies, the thermobalance was used to establish temperatures corresponding to equilibrium in the system, UO/sub 2/(s)-- UF/sub 4/(s)--HF(g) --H/sub 2/O(g), at several selected HF/H/sub 2/O ratios in the gas phase. These data, together with thermodynamic theory, were employed to calculate equilibrium conditions at total pressures other than one atmosphere and for various dilutions of the gas phase with an inert gas. (auth)
Date: March 12, 1958
Creator: Briggs, G.G.
Object Type: Report
System: The UNT Digital Library
Chemical Processing Department monthly report, February 1958 (open access)

Chemical Processing Department monthly report, February 1958

The February, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)
Date: March 21, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Chemical processing methods and economics for various liquid metal fuel reactors (open access)

Chemical processing methods and economics for various liquid metal fuel reactors

From abstract: "The economic factors of chemical processing of the fuel and blanket from liquid bismuth fuel reactors are described and evaluated."
Date: March 1958
Creator: Pierce, R. D.; Miller, W. E. & Zellnik, H. E.
Object Type: Report
System: The UNT Digital Library
Collapse : The Shock Heating of a Plasma (open access)

Collapse : The Shock Heating of a Plasma

There have been numerous independent suggestions to use high speed shocks to heat deuterium gas to thermonuclear temperature (E. Teller, R.R. Wilson, H. Grad, W. Marshall)², and extensive experimental work in this field is being carried on by, e.g., Kolb³, and S. Janes⁴. Our own work in this field has been directed towards a fundamental understanding of the strong shock process in the limit of no particle collision, to find out if within this limit the ion heating following the passage of the shock is large enough to give rise to a thermonuclear reaction.
Date: March 7, 1958
Creator: Colgate, Stirling A. & Wright, R. E.
Object Type: Report
System: The UNT Digital Library