A Theorectical Treatment of Atomic Configurations Found in Some Iron-Aluminum Solid Solutions (open access)

A Theorectical Treatment of Atomic Configurations Found in Some Iron-Aluminum Solid Solutions

"Theoretical calculations have been carried our for the two ordering phases which occur in the FeAl system. The statistical treatment involves first and second neighbor interaction parameters as well as a magnetic interaction between first neighbor iron atoms. The phase diagram and the amount and type of long range order for slowly cooled alloys are calculated. Further calculations include short range order for the disordered phase at three compositions and two temperatures. As expected, the short range order increases as a critical temperature is approached either in composition of in temperature."
Date: July 12, 1962
Creator: Houska, C. R.
Object Type: Report
System: The UNT Digital Library
Theoretical Considerations on Cell Shape, Convection, and an Area Anomaly Pertinent to Developing a Moving Boundary Theory for Ultracentrifugation (open access)

Theoretical Considerations on Cell Shape, Convection, and an Area Anomaly Pertinent to Developing a Moving Boundary Theory for Ultracentrifugation

The intuitive concept that a sector shaped centrifuge cell is free from convection is criticized. Not only is a form of convection present for a single sedimenting species, but a more insidious type occurs in a mixture having an appreciable Johnston-Ogston effect. Rather than striving for convection-free sedimentation, the proposal is to utilize if possible an apparently harmless type of convection occurring in a very thin annulus in order to avoid the convection extending between boundaries in a mixture. The requirement that the concentrations be independent of time meets this condition and yields a hyperbolic cell, which is approximated by a sector cell placed in the rotor backwards. Simultaneously, area measurements and calculations involving the Johnston-Ogston anomaly are simplified because of the time independence.
Date: July 8, 1952
Creator: Trautman, Rodes
Object Type: Report
System: The UNT Digital Library
Theoretical Studies of the Solidification of Uranium Castings (open access)

Theoretical Studies of the Solidification of Uranium Castings

Report discussing a method of evaluating factors relevant to the creation of sound uranium castings. From abstract: "A mathematical model has been developed to calculate the time-temperature relationships in a cylindrical uranium casting during its solidification. Finite-difference equations are used, and the solution is obtained by use of a digital computer."
Date: July 11, 1958
Creator: Fletcher, Billie L.; Foster, Ellis L., Jr.; Franklin, Charles K.; Lechler, Andrew; Schwartz, Benjamin L. & Dickerson, Ronald F.
Object Type: Report
System: The UNT Digital Library
Thermal and Hydraulic Design of the Consolidated Edison Thorium Reactor (open access)

Thermal and Hydraulic Design of the Consolidated Edison Thorium Reactor

This report presents the thermal and hydraulic analyses, both steady state and transient, for the CETR. Methods of calculations are discussed and results of analyses are presented. Steady state analyses are included for: pressure drops, flow distribution, orificing, burnout, fuel central melting, local boiling, and bulk boiling. Transient analyses are performed for several loss of forced coolant flow incidents.
Date: July 1960
Creator: Ferrell, J. K. (James K.); Flora, H. E.; Hostetler, D. R.; Stanek, L. J. & Vannoy, W. M.
Object Type: Report
System: The UNT Digital Library
Thermodynamics of Irreversible Processes: The Experimental Verification of the Onsager Reciprocal Relations (open access)

Thermodynamics of Irreversible Processes: The Experimental Verification of the Onsager Reciprocal Relations

Report discussing theories of irreversible thermodynamic processes. "The purpose of this review is to collect the presently available experimental data for a variety of quite different irreversible phenomena and to show that this evidence does indeed verify the Onsager Reciprocal Relations."
Date: July 30, 1959
Creator: Miller, Donald Gabriel
Object Type: Report
System: The UNT Digital Library
Thickness Vibrations in Long Rods of Barium Titanate (open access)

Thickness Vibrations in Long Rods of Barium Titanate

A theoretical analysis of the thickness vibrations in long thin rods of barium titanate is presented. The theoretical results are checked experimentally and their meaning discussed.
Date: July 29, 1955
Creator: Stephenson, C. V.
Object Type: Report
System: The UNT Digital Library
Thyratron Used as Combination Gate, Storage, and Driver for Punched Paper-Tape Output (open access)

Thyratron Used as Combination Gate, Storage, and Driver for Punched Paper-Tape Output

Report discussing a system designed to "punch binary data from an RCL pulse-height analyzer (PHA) on paper tape concurrent with the printing of decimal information."
Date: July 27, 1959
Creator: Walker, Robert M.
Object Type: Report
System: The UNT Digital Library
Time Dependence of the Beam in the 86-Inch Cyclotron (open access)

Time Dependence of the Beam in the 86-Inch Cyclotron

In the preliminary stages of getting up a time-of-flight system for measuring neutron spectra from proton reactions, a study of the time dependence of the beam in the 86Inch Cyclotron was made. This study revealed the expected bunching of the protons to produce a short burst of beam on each cycle of the 13.4 Mc/s accelerating voltage. In addition to the 13.4 Mc/s structure, however, there was a 360 c/sec modulation of the beam pulses and a complicated pattern built upon that.
Date: July 29, 1959
Creator: Goodman, C. D.
Object Type: Report
System: The UNT Digital Library
Transition Boiling Heat Transfer Program; Second Quarterly Progress Report, April - June 1963 (open access)

Transition Boiling Heat Transfer Program; Second Quarterly Progress Report, April - June 1963

Introduction: The Transition Boiling Heat Transfer Program is sponsored jointly by the USAEC and Euroatom and is being conducted by the General Electric Company. The work commenced on this program February 11, 1963. The objective of this program is to perform basic investigation and measurement of the transition boiling regime in high pressure bulk boiling water flows, with particular emphasis i the high range of steam qualities.
Date: July 1, 1963
Creator: Quinn, E. P.
Object Type: Report
System: The UNT Digital Library
Transition Boiling Heat Transfer Program; Sixth Quarterly Progress Report, April - June 1964 (open access)

Transition Boiling Heat Transfer Program; Sixth Quarterly Progress Report, April - June 1964

Summary: Transition boiling data was taken with an improved flow loop, to explore the influence of loop characteristics on rod temperature fluctuations the transition region was found to be much smaller than for comparable conditions with a different loop. Also the amplitude, and frequency of the temperature oscillations, were significantly less than before. These results indicate that loop characteristic and flow disturbance parameters play a prominent part in governing the transition temperature fluctuations. Additional two-rod transition boiling data are presented. The results include data taken at high wall temperature levels during a demonstration test at low steam qualities, and the effect of a change in rod spacing on heat transfer performance.
Date: July 1, 1964
Creator: Quinn, E. P.
Object Type: Report
System: The UNT Digital Library
Trip Rerport Organic Reactor Collant Survey (open access)

Trip Rerport Organic Reactor Collant Survey

A preliminary report has shown the potential importance of organic reactor coolants to Hanford technology. The salient points are complete avoidance of corrosion problems and accomplishment of DPR performance with low pressure technique. The recommendation of the report that loop tests be made at Hanford is to be acted upon by Recirculation Technology Unit as soon as organic coolant material is received. To insure starting this experimental work fully abreast of the information available, a trip to sites working with organic coolants was made. Specifically, data were sought on practical details of design for handling organic coolants, heat transfer and fouling characteristics, corrosion of materials, and hazards of handling organics.
Date: July 9, 1956
Creator: Atwood, J. K.; Cook, M. W. & Hanthorn, H. E.
Object Type: Report
System: The UNT Digital Library
UCRL Orbit Program (open access)

UCRL Orbit Program

The following report records the use of the double-precision THEMIS code to integrate the motion of Mars and Venus in order to obtain a complete set of rectangular equatorial coordinates over the interval 1600-2000 A.D.
Date: July 15, 1958
Creator: Levee, Richard & Brady, Joseph L.
Object Type: Report
System: The UNT Digital Library
UO2 Pellet Thermal Conductivity From Irradiations With Central Melting (open access)

UO2 Pellet Thermal Conductivity From Irradiations With Central Melting

Abstract: Continued irradiation experience under the AEC - Euratom, UO2 High Performance Program provided five separate and distinct sets of data on UO2 thermal conductivity. Four of these results are expressed in terms of the value of the thermal conductivity. The first two of these measurements were applicable -- strictly -- to poly crystalline UO2. Recently, three additional sets of measurements have been obtained -- all pertinent to UO2 after the formation of large columnar grains. The extent of melting in the experiments on which the results are based ranges from slight, to greater than 70 percent of the fuel cross section. The conclusions from all of these thermal conductivity measurements considered together are: (1) The true value of the UO2 conductivity integral form 0 degrees C to melting (2805 - 15 degrees C) lies in the range from 90 to 96 W/cm. The most probable value is closer to 90 W/cm. To ensure no central melting and the associated clad swelling the maximum thermal performance level for solid pellet, UO2 fuel rods should not exceed 90 W/cm. (2) Any improvement in thermal conductivity due to the formation of large, columnar UO2 grains is small and not detectable within the …
Date: July 1964
Creator: Lyons, M. F.; Coplin, D. H.; Pashos, T. J. & Weidenbaum, B.
Object Type: Report
System: The UNT Digital Library
Urine Analysis for Tritium Oxide (open access)

Urine Analysis for Tritium Oxide

This report analyzes a procedure based on the production of acetylene from the active water, with subsequent measurement of the ionization caused by the tritium beta particle. This eliminates the troublesome absorption on the chamber walls when hydrogen is used, and provides a rapid method for the preparation of the urine samples.
Date: July 27, 1949
Creator: Healy, J. W.
Object Type: Report
System: The UNT Digital Library
Use Of Pyroelectric Devices For Measuring Small Temperature Changes (open access)

Use Of Pyroelectric Devices For Measuring Small Temperature Changes

A technique for measuring extremely small temperature changes by means of a pyroelectric device is described. The sensing element is a short thin rod of polarized barium titanate ceramic with electrodes on the ends. The electric charges produced by changes in temperature are measured by a vibrating-reed electrometer. A number of calorimetric and noncalorimetric applications for the device are suggested.
Date: July 1960
Creator: Lang, Sidney B.
Object Type: Report
System: The UNT Digital Library
The Use of the Electrical Conductivity of Graphite as a Radiation Damage and Flux Monitor. Implications of the Results to the General Theory of Radiation Damage (open access)

The Use of the Electrical Conductivity of Graphite as a Radiation Damage and Flux Monitor. Implications of the Results to the General Theory of Radiation Damage

A method for monitoring radiation damage irradiations using the change of the electrical conductivity of graphite is described. Results of monitoring operations in a number of locations are given. An attempt is made to explain the damage rate found in the converter at CP-3. An estimate of the flux spectrum in VT-4 and the converter of CP-3 is made and the damage rate is computed according to theories of Seitz and James. It is found that the experimental results are more in accord with the predictions of Seitz. A number of corrections to James' report, ORNL-307, are noted in an appendix. It is shown that some information about the fast flux spectrum can be inferred from the radiation damage rate.
Date: July 13, 1953
Creator: Primak, W. L. & Fuchs, L. H.
Object Type: Report
System: The UNT Digital Library
Utex Ore Stockpiled at Monticello (open access)

Utex Ore Stockpiled at Monticello

A program of bench scale leaching and ion exchange testing for the recovery of uranium from liquors produced by leaching Utex ore (Monticello Stockpile 28) was conducted at Monticello, Utah from July 1953 to April 1954.
Date: July 19, 1954
Creator: Moulton, Harry D.
Object Type: Report
System: The UNT Digital Library
Vapor-Deposited Zirconium on Uranium (open access)

Vapor-Deposited Zirconium on Uranium

From introduction: "This report describes the second phase of the work on the application of protective coatings to uranium by vapor deposition to reduce or prevent its corrosion by water."
Date: July 20, 1955
Creator: Powell, Carroll F.; Jones, Robert P.; Girod, Fleet T. & Campbell, Ivor E.
Object Type: Report
System: The UNT Digital Library
The Volatilization of Fission Products by Melting of Reactor Fuel Plates (open access)

The Volatilization of Fission Products by Melting of Reactor Fuel Plates

Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of the rare gases; the halogens, iodine and bromine; and the alkali metals, cesium and rubidium. In the presence of air or water vapor, strontium and other fission products are not released. At trace concentration of fission products, slow melting of the APPR plate at 1525 C in air or steam effected the release of 50 percent of the rare gases, 33 percent of the iodine, 9 percent of the cesium and traces of strontium. After 25% burn-up, the cesium value increased to about 60 percent. Aluminum alloy of the MTR type, also at trace concentration, upon melting at 700 C released up to 2 percent of the iodine, 10 percent of the rare gases, and negligible portions of other fission products. Zirconium alloy of the STR type after 15 percent burn …
Date: July 15, 1957
Creator: Parker, Geogre W. & Creek, George E.
Object Type: Report
System: The UNT Digital Library
Water Adsorbed by Graphite at Various Relative Pressures (open access)

Water Adsorbed by Graphite at Various Relative Pressures

Summary: "The quantity of water adsorbed by graphite at various relative pressures has been determined and the data are presented in graphical and tabular form."
Date: July 21, 1953
Creator: Spalaris, C. N.
Object Type: Report
System: The UNT Digital Library
Water Spectra and Energy Exchange Kernels (open access)

Water Spectra and Energy Exchange Kernels

Many measurement of neutron spectra have been made in water assemblies. In these system a large part of the spectrum is given by an essentially Maxwellian distribution at the moderator temperature which is insensitive to the scattering model. Hence, the test of the energy exchange scattering kernel is in the difference of the spectrum and the fundamental or Maxwellian component. The figure shows the spectrum for the Nelkin model. Once the fundamental has been subtracted neither theoretical model seems to fit the data extremely well. Below kT the Nelkin model is a closer fit than the gas model but it underestimates the deviation from the Maxwellian whereas in the joining region it overestimates the distortion.
Date: July 11, 1963
Creator: Daitch, Paul B. (Paul Bernard), 1925- & Ohanian, M. J.
Object Type: Report
System: The UNT Digital Library
Welding Characteristics of Zircaloy Jacketed Fuel Elements (open access)

Welding Characteristics of Zircaloy Jacketed Fuel Elements

Contemplated higher tube power for future reactor operation will probably require a fuel element jacketing material more corrosion resistant than presently available aluminum alloys. Zirconium and its alloys are generally regarded as the most promising jacketing candidates for high temperature operation, particularly for exposures of long duration. In order to obtain assembly, welding, and corrosion data, twenty Al-Si bonded and twenty unbonded Zircaloy fuel elements were prepared for KER loop testing. This report describes the technique developed to weld Zircaloy jacketed fuel elements and presents the results of end closure corrosion testing and metallographic examination.
Date: July 1, 1956
Creator: Lingafelter, J. W.
Object Type: Report
System: The UNT Digital Library
Zircaloy-2 Sheet and Strip Material (open access)

Zircaloy-2 Sheet and Strip Material

Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Object Type: Report
System: The UNT Digital Library
Zircaloy-2 Tubing for Fuel Sheathing (open access)

Zircaloy-2 Tubing for Fuel Sheathing

Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
Object Type: Report
System: The UNT Digital Library