A Dynamic Method For Mercury Vapor Detector Calibration (open access)

A Dynamic Method For Mercury Vapor Detector Calibration

The calibration of mercury vapor detectors has always posed a problem because of the difficulty of generating known concentrations of mercury vapor in air. The purpose of this study was to design an apparatus that would generate and chemically measure known concentrations of mercury vapor in air for calibration work.
Date: February 21, 1964
Creator: Nelson, Gary O.; Van Sandt, Walter & Barry, Patrick
Object Type: Report
System: The UNT Digital Library
Contained Nuclear Detonations in Four Media - Geological Factors in Cavity and Chimney Formation (open access)

Contained Nuclear Detonations in Four Media - Geological Factors in Cavity and Chimney Formation

Recent underground nuclear tests conducted by the U.S. Atomic Energy Commission have yielded data on the effects of contained nuclear explosions in four rock mediums: tuff, alluvium, rock salt, and granite. This report presents and compares data obtained primarily through exploratory mining and drilling into the postshot environment of 35 such events.
Date: April 24, 1964
Creator: Boardman, Charles R.; Rabb, David D. & McArthur, Richard D.
Object Type: Report
System: The UNT Digital Library
Nuclear Excavation Technology (open access)

Nuclear Excavation Technology

Nuclear excavation is the name given to the concept of using large scale nuclear explosion craters for useful projects, such as harbors, canals, and roadway cuts. It is one of the principal applications of the Plowshare Program for industrial, or peaceful, uses of nuclear explosives. Plowshare is sponsored by the U.S. Atomic Energy Commission and is under the technical direction of the Lawrence Radiation Laboratory at Livermore, California. The purpose of this paper is to describe cratering concepts and the present state of nuclear excavation technology. The general nature of the safety hazards associated with nuclear excavation are also discussed.
Date: February 10, 1964
Creator: Nordyke, Milo D.
Object Type: Report
System: The UNT Digital Library
Preburst Resistance and Temperature of Exploding Wires (open access)

Preburst Resistance and Temperature of Exploding Wires

It has been shown that the time of burst of exploding wires can be predicted from known thermodynamic and electrical properties of the wire materials under some conditions. The mathematical relationships are a set of integrals (transformation time integrals) similar in form to the empirical "action integrals" sometimes used in exploding wire work. This paper discusses the use of the transformation time integrals to calculate the resistance and temperature of a wire as a function of time up to the time of burst and to investigate the effects of environment of the wire on the temperature, resistance, and time of burst.
Date: February 24, 1964
Creator: Maninger, R. C.
Object Type: Report
System: The UNT Digital Library
Re-entry Flight Demonstration Number One (RFD-1): Atmospheric Sciences Support (open access)

Re-entry Flight Demonstration Number One (RFD-1): Atmospheric Sciences Support

Abstract: Data from the atmospheric sciences support systems for RFD-1 on May 22, 1963, at Bermuda Island, are presented. These data were taken for purposes of later analysis of the ballistic performance of the re-entry vehicle and of the heat transfer mechanisms within it, and for studies of the motion of ablated particles in the atmosphere.
Date: October 1964
Creator: Coonce, C. A.
Object Type: Report
System: The UNT Digital Library

Plates 1-4: Aeroradioactivity Map (ARMS-II), Parr Area, South Carolina and North Carolina

Maps of four quadrants in the Parr area surveyed as part of a radiological survey, outlining "Radioactivity levels in hundreds of counts per second normalized to 500 ft above ground." Scale 1:250,000.
Date: 1964
Creator: Edgerton, Germeshausen & Grier
Object Type: Map
System: The UNT Digital Library

Plates 1-3: Aeroradioactivity Map (ARMS-II), Orlando Area, Florida

Maps of three segments in the Orlando area surveyed as part of a radiological survey, outlining "Radioactivity levels in hundreds of counts per second normalized to 500 ft above ground." Scale 1:250,000.
Date: April 1964
Creator: Edgerton, Germeshausen & Grier
Object Type: Map
System: The UNT Digital Library

Plate 1. Natural Gamma Aeroradioactivity and Generalized Geologic Maps of Puerto Rico

Map with graded color shading to show levels of naturally-occurring gamma aeroradioactivity within Puerto Rico. Details about the survey and map creation are printed at right. Scale 1:250,000.
Date: March 1964
Creator: MacKallor, Jules A.
Object Type: Map
System: The UNT Digital Library

Plate 1. Natural Gamma Aeroradioactivity of the GNOME (Carisbad) Area, New Mexico and Texas

Map with graded color shading to show levels of naturally-occurring gamma aeroradioactivity within the "Gnome" test area in New Mexico and Texas. Details about the survey and map creation are printed at right. Scale 1:250,000.
Date: 1964
Creator: MacKallor, Jules A.
Object Type: Map
System: The UNT Digital Library
Respiratory Protective Equipment, A Final Report (open access)

Respiratory Protective Equipment, A Final Report

"Properly designed and fitted respirators have been effective devices for reducing the inhalation of toxic aerosols. The degree of protection afforded by these devices has not been quantitatively measured under actual work conditions except by bioassay or other elaborate techniques. This report describes a new quantitative technique for evaluating over-all respiratory performance under conditions comparable to exposure to highly toxic radioactive materials such as plutonium and non-radioactive materials such as beryllium."
Date: June 30, 1964
Creator: Silverman, Leslie & Burgess, William A.,1924-
Object Type: Report
System: The UNT Digital Library
Foam Suppression of Radioactive Iodine and Particulates (open access)

Foam Suppression of Radioactive Iodine and Particulates

" A reliable, efficient and economical method is needed to remove radioactive halogens such as iodine and bromine and particulates from air in many atomic energy installations. One method we have developed which is particularly suited to reactor containment vessels or other large confined areas is foam containment. In this method an ether lauryl sulfate foam containing an iodine reactant is generated, rapidly filling the entire containment volume. This provides a tremendous surface area to which the encapsulated gases and particles can diffuse and be removed."
Date: February 25, 1964
Creator: Yoder, Robert E.; Fontana, Mario H. & Silverman, Leslie
Object Type: Report
System: The UNT Digital Library
The Thermal Decomposition of Uranium Mononitride (open access)

The Thermal Decomposition of Uranium Mononitride

The use of uranium mononitride as a nuclear fuel is being considered for a number of high temperature applications. In comparison with the most often applied high temperature fuels, UO2 and UC, one finds that UN has a combination of the high melting point of UO2 and the thermal conductivity and high uranium density of UC. However, interest in UN is often dampened by qualitative indications of its low thermal stability and by lack of experimental thermodynamic data. Is is the purpose of this study, therefore, to provide a quantitative measure of the thermal stability of UN and to establish some of its thermodynamic properties.
Date: January 7, 1964
Creator: Vozzella, P. A.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
Object Type: Report
System: The UNT Digital Library
The Thermal Conductivity of Uranium Monocarbide (open access)

The Thermal Conductivity of Uranium Monocarbide

Uranium carbide shows promise as a fuel material for reactors operating at relatively high temperatures based on its high melting point, high uranium density and high thermal conductivity. Before refined reactor designs can be made, however, good quantitative data on the thermal conductivity at temperatures in excess of 1000C is required. This technical report presents data gathered as part of a continuing study aimed at determining the thermal conductivity of refractory uranium fuels as a function of temperature, density and composition over the temperature range 1000-2200C. At the inception of this program it was felt that an absolute method capable of achieving high temperatures was necessary and that the difficulties encountered in fabricating the large complex specimens needed were justified. The steady state radial heat flow method and apparatus of Rasor and McClelland were therefore chosen. The technical report discusses the experimental equipment and presents results of measurements on three specimens of UC over a temperature range 900 to 1600C. An analysis of the data is made with respect to other physical properties of the material and the measured conductivities are compared with the work of other investigators.
Date: April 2, 1964
Creator: Sobon, J. T.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
Object Type: Report
System: The UNT Digital Library
Sintering Studies on Ceramic Fuel Materials (open access)

Sintering Studies on Ceramic Fuel Materials

Satisfactory dense crack—free dispersions of spheroidal UO2 — ThO2 particles in BeO can be produced by "co-sintering", a process in which unsintered particles are hydrostatically pressed in BeO and the dispersion is sintered in one step, the large voids and cracks in dispersions of fully sintered particles in BeO following sintering are related to mismatched sintering shrinkage between the two phases; they are probably indicative of a high interfacial energy between the two phases. Co—sintering has been used for individual fabrication of specimens for irradiation testing, but is not immediately applicable to large scale fabrication of fuel element shapes, Possible modifications of the method are discussed.
Date: January 1964
Creator: Reeve, Keith Desmond, 1928- & Jones, K. A.
Object Type: Report
System: The UNT Digital Library
Case Reports -- 1962.  Cytomegalic Inclusion Disease of the Submaxillary Gland. Etiologic Factors in Obstruction of the Superior Vena Cava (open access)

Case Reports -- 1962. Cytomegalic Inclusion Disease of the Submaxillary Gland. Etiologic Factors in Obstruction of the Superior Vena Cava

The case history and autopsy finding are presented for a case of cytomegalic inclusion disease in the salivary glad of a 5-month-old male infant. The relation of viruses to cytomegalic inclusion disease is discussed briefly. The etiologic factors in obstruction of the superior vena cava in a group of cases that came to necropsy are discussed.
Date: 1964
Creator: Niwayama, Gen, 1929-
Object Type: Report
System: The UNT Digital Library
Adult Health Study : Review of Substudies, June 1962, Hiroshima and Nagasaki (open access)

Adult Health Study : Review of Substudies, June 1962, Hiroshima and Nagasaki

Data are summarized from a series of studies to determine the late effects of radiation in adult populations of Nagasaki and Hiroshima. Results ae reported from studies on skin aging, hair greying, cardiovascular findings, neuromuscular response, antibody levels, ocular aging, auditory aging, and miscellaneous aging characteristics in persons exposed to radiation from the atomic bombs as adults; growth and development studies on exposed persons born between 1935 and 1945; the incidence of neoplasms in the exposed populations; possible genetic effects of radiation in selected groups; the incidence of tuberculosis and other infectious diseases in exposed populations; hematological studies; metabolic studies, and other related studies in exposed persons and their offspring. Possible future programs are discussed.
Date: 1964
Creator: Finch, Stuart C.
Object Type: Report
System: The UNT Digital Library
ABCC-NIH Adult Health Study Hiroshima 1958-60. Cardiovascular Project Report Number 6, Heart Size Norm (open access)

ABCC-NIH Adult Health Study Hiroshima 1958-60. Cardiovascular Project Report Number 6, Heart Size Norm

Data on 13,000 person 15 yr of age or older obtained during detailed clinical examinations, including radiological recorded heart size, were correlated with sex, age, height, and weight of subjects to arrive at a standard heart size for Hiroshima residents This information will be used in investigations cardiovascular disease in the population.
Date: 1964
Creator: Ueda, Shoichi; Russell, Walter J. & Yano, Katsuhiko
Object Type: Report
System: The UNT Digital Library
The ScCl3-Sc System (open access)

The ScCl3-Sc System

Experimental data supporting lower valence halides of scandium were not found in the literature. Our investigation was of the phase diagram of the ScCl3-Sc system, and also the vapor pressure-composition isotherm (at 960 degree) for this system. Investigation of the ScCl3-Sc system presented particular difficulties in comparison with analogous systems for rare earth elements in that ScCl3 is highly volatile (boiling pt. = 967 degree); according to our data the vapor pressure is 512 mm Hg measured at 960 degree C. Furthermore, ScCl3 and its vapors react vigorously with quartz. Because of the mentioned extent of reaction in a quartz ampule, the inside was covered with a solid layer of metallic molybdenum for use with relatively large batches of ScCl3.
Date: April 1964
Creator: Polyachenok, O. G. & Novikov, G. I.
Object Type: Report
System: The UNT Digital Library
Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed (open access)

Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed

The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several points up the reactor and there may be continuous or intermittent addition of fresh fuel and removal of residue ash.
Date: August 13, 1964
Creator: Scott, Charles D.
Object Type: Report
System: The UNT Digital Library
Graduate Programs for the Health Physicist in the United States (open access)

Graduate Programs for the Health Physicist in the United States

The first man-made nuclear reactor -- or "pile" as it was then called -- was rather hurriedly improvised and operated in a crowded space under the athletic bleachers of Stagg Field at the University of Chicago on December 2, 1942. Just prior to this time, there began the assembly of a group of physicists with an unusual assignment. They were determined that radiation hazards of unprecedented proportions must be coped with successfully in the conduct of reactor programs as planned. Since these physicists were to be concerned with the health of radiation workers, they were called health physicists. There was no formal instruction available to this first group of health physicists and they perforce received training as they felt their way by firsthand experience and by trial and error. Health physics at Oak Ridge National Laboratory from the very beginning has been organized into three principal areas: applied activities, education and training and research.
Date: August 13, 1964
Creator: Morgan, K. Z. (Karl Ziegler), 1908-
Object Type: Report
System: The UNT Digital Library
Thermal Properties of Grade CGB Graphite (open access)

Thermal Properties of Grade CGB Graphite

Grade CGB graphite is a nuclear graphite which is basically an extruded petroleum coke bonded with coal tar pitch. No carbon blacks are used and the low-permeation graphite is finished through a series of impregnations and heat treatments with a final heat treatment of all components to 2800 degrees C. A listing of the results obtained is given in Table 1. The results at 51 degrees C are considered questionable. There was a slight contamination of the 90% Pt 10% Rh-Pt thermocouples at 910 degrees C but it was not sufficient to doubt the validity of the 910 degrees C results. However, the results obtained at 1015 degrees C should be disregarded because of severe thermocouple instabilities. In addition, the electrical resistance of the core heater at 603 degrees C indicated the thermocouples had a -10 to -15 degree error which is sufficient justification to disregard the 605 degrees C data.
Date: August 11, 1964
Creator: Moore, J. P. & Godfrey, T. G.
Object Type: Report
System: The UNT Digital Library
Comparison of the Thermal Conductivity, Electrical Resistivity, and Seebeck Coefficient of a Hight-Purity Iron and Armco Iron to 1000 [degrees] C (open access)

Comparison of the Thermal Conductivity, Electrical Resistivity, and Seebeck Coefficient of a Hight-Purity Iron and Armco Iron to 1000 [degrees] C

The thermophysical properties of Armco iron such as thermal conductivity, electrical resistivity, and Seebeck coefficient have been extensively investigated and reviewed up to 1000 degrees C. Few investigations of such properties have been made on high purity iron. If such a study is made using the same apparatus to determine the properties of two purity levels of iron, then several significant intercomparisons can be made which add meaning to data on a single material. The systemic errors for a single apparatus are the same, therefore comparison of a property of two similar materials is more significant. A comparison of the property changes with temperature and purity can show the effects of impurities on the mechanisms contributing to a property and allows prediction of the properties of iron as a function of purity. For these reasons a study was initiated on the high-purity iron for comparison to Armco iron.
Date: August 11, 1964
Creator: Moore, J. P.; Fulkerson, W. & McElroy, D. L.
Object Type: Report
System: The UNT Digital Library
A Thermal Comparator Apparatus for Thermal Conductivity Measurements from 50 to 400 [degrees] C (open access)

A Thermal Comparator Apparatus for Thermal Conductivity Measurements from 50 to 400 [degrees] C

The experimental details, mathematical models, and typical data for a rapid comparative method for thermal conductivity measurements are presented. The method consists of measuring the temperature change of a small silver sphere after it is brought in contact with a small disk-shaped specimen which was initially at ta higher temperature. This temperature change was calibrated in the range of 50 to 400 degrees C by making measurements on samples of know thermal conductivity. The accuracy of this technique was shown to be between than +-10% with a reproducibility of at least +-2.5%. Using known transport mechanisms for heat conduction in solids and the temperature dependency of the electrical conductivity, a means to judiciously extrapolate thermal conductivity data obtained between 50 and 400 degree C to high temperature is presented.
Date: August 11, 1964
Creator: Kollie, T. G.; McElroy, D. L.; Graves, R. S. & Fulkerson, W.
Object Type: Report
System: The UNT Digital Library
Recent Developments in DC Polarography (open access)

Recent Developments in DC Polarography

This paper summarized the work at ORNL in controlled-potential dc polarography since mid 1959 and states conclusion and viewpoints that have been reached in the course of this work. The following topics are discussed: (1) Potentiostatic Compensation for Polarographic Cell Resistance; (2) Time-Derivative DC Polarography; (3) Signal-to-Noise Ratio (S.N); (4) Resolution; and (5) DC Polarography in Non Aqueous Solvents and, Particularly, in Solvent Extracts.
Date: July 1964
Creator: Fisher, D. J.; Belew, W. L. & Kelley, M. T.
Object Type: Report
System: The UNT Digital Library