In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans (open access)

In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans

Scintillation spectrometry is used to measure the gamma activity from uranium for determining lung burden in the human body.
Date: June 23, 1959
Creator: Cofield, Rogers E.
System: The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959

Introduction: "This is the seventh letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from April 1 to May 31, 1959."
Date: June 15, 1959
Creator: Stockham, John D. & Rosinski, John
System: The UNT Digital Library
Investigation of Graphite Bodies : Progress Report No. 3 for the Period March 1, 1959 to May 31, 1959 (open access)

Investigation of Graphite Bodies : Progress Report No. 3 for the Period March 1, 1959 to May 31, 1959

This document is the third in a series of progress report that records investigations of graphite bodies. Along with the report, two appendices are given to describe the different graphite bodies: "Synthetic Binders for Carbon and Graphite" and "High Temperature Physical Properties of Molded Graphites".
Date: June 10, 1959
Creator: Bradstreet, Samuel W.
System: The UNT Digital Library
Radiation Shielding for Test Cell "C" (open access)

Radiation Shielding for Test Cell "C"

"This report contains information on the following topics related to the radiation shielding at test cell "C". (1) Calculation of wall and roof thicknesses. (2) Calculation of radiation heating of front wall by gamma and neutron absorption. (3) Calculation of neutron activation in front face of test cell. (4) Calculation of γ-dose rates both direct and behind shadow shields at various distances. (5) Dose produced by a reactor catastrophe."
Date: June 1959
Creator: Fenstermacher, Charles Alvin & Henshall, James
System: The UNT Digital Library
An Improved Nuclear Density Gauge : Covering the Interval of June 1 to July 1, 1959 (open access)

An Improved Nuclear Density Gauge : Covering the Interval of June 1 to July 1, 1959

The following document is a note describing the building process of an improved nuclear density gauge in comparison to previous gauges, within the interval of June 1 to July 1, 1959.
Date: June 8, 1959
Creator: Burgwald, G. M. & Stone, C. A.
System: The UNT Digital Library
Proceedings of the Sixth Tripartite Instrumentation Conference, Part 3: System and Component Reliability (open access)

Proceedings of the Sixth Tripartite Instrumentation Conference, Part 3: System and Component Reliability

Collection of papers presented during the third session (Tuesday, April 21, 1959) at the 6th Tripartite Instrumentation Conference. The five papers describe reliability, maintenance, and failure of electronic equipment and other components in reactors at Chalk River (Canada), Harwell (U.K.), and Oak Ridge (U.S.).
Date: June 1959
Creator: Woolston, J. E. & Townsend, S. J.
System: The UNT Digital Library
Shielding Against Magnetic Radiation Loss from a Hot Plasma (open access)

Shielding Against Magnetic Radiation Loss from a Hot Plasma

Abstract: "Classical electromagnetic theory indicates that a conducting metallic shield can reduce the magnetic-radiation loss from a hot plasma (centrally located) undergoing D-D burn to less than 1%, or two orders of magnitude."
Date: June 1959
Creator: Wesley, James Paul
System: The UNT Digital Library
The Nuclear Ramjet Propulsion System (open access)

The Nuclear Ramjet Propulsion System

The following report describes the workings and development of the nuclear ramjet propulsion systems.
Date: June 30, 1959
Creator: Merkle, Theodore C.
System: The UNT Digital Library
The Satellite Code: A Numerical Satellite Integration Program for the IBM 704 (open access)

The Satellite Code: A Numerical Satellite Integration Program for the IBM 704

From Introduction: "This report is intended as a handbook for the users of the Satellite code which was developed as a general purpose satellite and space probe program. The components of acceleration, in a three-dimensional rectangular coordinate system, are integrated to produce the velocities and coordinates. These may be transformed into elliptical elements at each time step. The output, therefore, may resemble an integration in the coordinates as well as in the parameters."
Date: June 1959
Creator: Smith, Virginia S.; Bruijnes, Hans R. & Sherman, Nevin W.
System: The UNT Digital Library
Gamma Rays from the Interaction of 14-Mev Neutrons with Beryllium (open access)

Gamma Rays from the Interaction of 14-Mev Neutrons with Beryllium

Abstract: "The cross section for the Be-9(n, t')Li-7*-->Li-7 + Y(0.477 Mev) reaction has been measured in the vicinity of 14 Mev by detecting the gamma-rays at scattering angles from 30 to 150 degrees. A time-of-flight technique was used to distinguish the gamma-rays from the high neutron background. The cross section drops from 20 mb at 13.6 Mev to 10 mb at 14.1 Mev and then rises to 30 mb at 14.7 Mev."
Date: June 9, 1959
Creator: Benveniste, J.; Mitchell, A. C.; Schrader, C. D. & Zenger, J. H.
System: The UNT Digital Library
Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR (open access)

Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR

From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."
Date: June 1, 1959
Creator: Parkinson, W. W. & Sisman, O.
System: The UNT Digital Library
A Study of Reactor Systems for the Production of Tritium and Radioactive Cobalt (open access)

A Study of Reactor Systems for the Production of Tritium and Radioactive Cobalt

"A conceptual design study of reactors for the join production of tritium and colbat-60 has been made. The study covered a family of four reactors raging in thermal power from 16.5 MW to 150 MW, and designed for corresponding annual productions ranging from 0.5 to 5.0 million curies of tritium respectively."--P. v.
Date: June 8, 1959
Creator: unknown
System: The UNT Digital Library
An Exploding Wire as a Fuse for the LASL Capacitor Bank--Zeus (open access)

An Exploding Wire as a Fuse for the LASL Capacitor Bank--Zeus

Abstract: "An exploding copper wire, one millimeter in diameter, 30 centimeters long, has been developed as a fuse component for a Los Alamos capacitor energy source to be employed in controlled thermonuclear research studies. The fuse allows the passage of the high normal duty "action" (13,700 ampere-coulombs per capacitor) at a 20-second repetition rate. However, it interrupts the circuit to a shorted capacitor in 12 microseconds, thereby protecting the faulted capacitor from explosive energy consumption. The initial phase of the development included observations of various metals (copper, silver, iron, and nickel) as well as various configurations (straight wires, helixes, foils, and tubes). Direct scaling of previous small exploding wire studies at Sandia Corporation was demonstrated with scaling factors up to 700,000."
Date: June 4, 1959
Creator: Cnare, Eugene C.
System: The UNT Digital Library
Geologic Summary of the San Juan Basin, New Mexico, with Reference to Disposal of Liquid Radioactive Waste (open access)

Geologic Summary of the San Juan Basin, New Mexico, with Reference to Disposal of Liquid Radioactive Waste

From introduction: Approximately fifty radioactive deposits and nearly fifty properties not abnormally radioactive were examined during a geologic reconnaissance for radioactive minerals in Idaho, Washington, and western Montana during the period July 1952 -- June 1955. The most important uranium deposits are in or near granitic to quartz monzonitic intrusions of probable Cretaceous age in central and northern Idaho, westernmost Montana, and northeastern Washington. The purpose of these reports is to describe the geology of the areas so that the possibilities for the disposal of high-level radioactive fluid waste in deep wells can be ascertained.
Date: June 1959
Creator: Repenning, Charles Albert
System: The UNT Digital Library
Summary of Some Physical Data from Five Vertical Drill Holes Over the U12b.04 (Evans) Explosion Chamber, Nevada Test Site, Nye County, Nevada (open access)

Summary of Some Physical Data from Five Vertical Drill Holes Over the U12b.04 (Evans) Explosion Chamber, Nevada Test Site, Nye County, Nevada

From introduction: This report details the results of instrument recordings of a nuclear explosion where ground zero was near the top of Rainier Mesa.
Date: June 1959
Creator: Poole, Forrest G. & Roller, John C.
System: The UNT Digital Library
Chemical Composition as a Guide to the Size of Uranium Deposits in the Salt Wash Member of the Morrison Formation, Colorado Plateau (open access)

Chemical Composition as a Guide to the Size of Uranium Deposits in the Salt Wash Member of the Morrison Formation, Colorado Plateau

Report discussing the use of chemical concentrations of certain elements in uranium deposits of the Colorado Plateau as a guide for the size of the deposits.
Date: June 1959
Creator: Miesch, A. T.; Shoemaker, E. M.; Newman, W. L. & Finch, W. I.
System: The UNT Digital Library
Distribution of Elements in Sedimentary Rocks of the Colorado Plateau (open access)

Distribution of Elements in Sedimentary Rocks of the Colorado Plateau

Report discussing a study of the distribution, volume, and lithologies of sedimentary rocks of the Colorado Plateau, and of the distribution of elements contained within these rocks.
Date: June 1959
Creator: Newman, William L.; Shoemaker, E. M. & Miesch, A. T.
System: The UNT Digital Library
Geologic Investigations of Radioactive Deposits Semiannual Progress Report, December 1, 1958 to May 31, 1959 (open access)

Geologic Investigations of Radioactive Deposits Semiannual Progress Report, December 1, 1958 to May 31, 1959

The following is a semiannual progress report, preliminary in nature, covering work done in the period of December 1, 1958 to May 31, 1959.
Date: June 1959
Creator: Geological Survey (U.S.)
System: The UNT Digital Library
Transistorized Log-Period Amplifier (open access)

Transistorized Log-Period Amplifier

Abstract: A log-period amplifier which is combined with power supply on a rack-mounted chassis with a 7-in. panel is described.
Date: June 1959
Creator: Wade, E. J. & Davidson, D. S.
System: The UNT Digital Library
Status and Future Program of Homogeneous Reactor Fuel Processing Studies (open access)

Status and Future Program of Homogeneous Reactor Fuel Processing Studies

The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress.
Date: June 17, 1959
Creator: Burch, W. D.; Haas, P. A. & McNees, R. A.
System: The UNT Digital Library
Hexone Extraction-Coulometric Titration of Uranium (open access)

Hexone Extraction-Coulometric Titration of Uranium

Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.
Date: June 22, 1959
Creator: Blevins, E. L.
System: The UNT Digital Library
Fuel Cycle Cost for Aqueous Homogeneous Reactors (open access)

Fuel Cycle Cost for Aqueous Homogeneous Reactors

By using a large central fuel and blanket reprocessing facility, slurry-fueled aqueous homogeneous reactors can attain an estimated minimum fuel cycle cost of 1.4-1.6 mills/kwh; with solution-fueled two-region reactors, a doubling time of 14 years may be obtained at a fuel cycle cost of 2.0 mills/kwh. On-site processing appears desirable only for large power stations made up of reactors designed for short doubling times. For instance, a solution-fueled two-region reactor can attain a 12-year doubling time at an estimated fuel cycle cost of 1.5 mills/kwh at a 2000 Mw electricity station with an on-site processing plant.
Date: June 2, 1959
Creator: Culler, F. L.
System: The UNT Digital Library
Internally Cooled Molten-Salt Reactors (open access)

Internally Cooled Molten-Salt Reactors

The initial and long-term nuclear characteristics of two internally cooled heterogeneous, graphite-moderated, two-region, molten-salt reactors have been studied. These reactors have doubling times of 22.5 years and 27.5 years. Methods of decreasing the doubling times by removing the Pa233 from the core and be increasing the specific power of the reactor are described.
Date: June 22, 1959
Creator: Lackey, M. E.
System: The UNT Digital Library
Lecture Notes on Reactor Controls (open access)

Lecture Notes on Reactor Controls

This course on reactor controls is for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. This material is the outgrowth of the notes prepared for the lectures on Reactor Controls given in the Oak Ridge School of Reactor Technologu. The lectures given by T. E. Cole in 1953-1955 are the basis of portions of the subject matter on reactor kinetics. Many suggestions and ideas contributed by E. R. Mann are included throughout almost every section. In addition, several members of the Oak Ridge National Laboratory, and of the Reactor Controls Department in particular, have provided information which has been included in these lectures notes.
Date: June 24, 1959
Creator: Walker, C. S.
System: The UNT Digital Library