Gas Cooled Nuclear Reactor Study (open access)

Gas Cooled Nuclear Reactor Study

Study of a gas cooled reactor with design specifications providing for a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas-turbine power plant.
Date: July 31, 1956
Creator: Thompson, A. S.
System: The UNT Digital Library
Joint Design for Making Root Pass Welds without Filler Material (open access)

Joint Design for Making Root Pass Welds without Filler Material

Investigation to evaluate some of the designs, techniques, and methods for fabrication of a root pass.
Date: July 9, 1956
Creator: Lemon, L. C. & Smith, W. R.
System: The UNT Digital Library
Engineering Test Reactor : Engineering Design and Safeguards Report (open access)

Engineering Test Reactor : Engineering Design and Safeguards Report

From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
Date: July 1956
Creator: Kaiser Engineers
System: The UNT Digital Library
Program Study Report Plutonium Fuel Cycle (open access)

Program Study Report Plutonium Fuel Cycle

From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date: July 30, 1956
Creator: Albaugh, F. W. & Fryar, R. M.
System: The UNT Digital Library
Polonium (open access)

Polonium

From foreword: This is a report on the efforts of Monsanto Chemical Co. to solve some of the chemical problems involved in the atomic energy program.
Date: July 1956
Creator: Moyer, Harvey Vernon; Gnagey, Lloyd B. & Rogers, Adrian J.
System: The UNT Digital Library
Preliminary Report on a Uranium Occurrence and Regional Geology in the Cherry Creek Area, Gila County, Arizona (open access)

Preliminary Report on a Uranium Occurrence and Regional Geology in the Cherry Creek Area, Gila County, Arizona

Introduction: A reconnaissance of the Black Brush property was made by geologists of the Atomic Energy Commission in March, 1955. This anomalous area was located by an earlier airborne radiometric survey. the examination consisted of preliminary sampling and surface and underground radiometric traversing.
Date: July 1956
Creator: Sharp, Byron J.
System: The UNT Digital Library
Some Preliminary Investigations in the Use of a Supersonic Mercury Vapor Jet for Providing an Energetic Neutral Beam (open access)

Some Preliminary Investigations in the Use of a Supersonic Mercury Vapor Jet for Providing an Energetic Neutral Beam

Report discussing experiments conducted under the Livermore "Waldo" project to determine "(1) surface densities attainable in a supersonic mercury vapor jet stream, (2) the approximate efficiency of a mercury jet for neutralizing a proton beam, and (3) the mercury partial pressure contribution in the bore due to side streaming from the mercury jet."
Date: July 18, 1956
Creator: Steinhaus, J. F.
System: The UNT Digital Library
Progress Relating to Civilian Applications During June, 1956 (open access)

Progress Relating to Civilian Applications During June, 1956

A report about the mechanical properties of dilute uranium alloys which might be crucial to developing high strength alloys for possible use as fuel.
Date: July 2, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment:  Quarterly Technical Report No. 1, BAW-1001, July 1, 1956 to November 15, 1956 (open access)

Liquid Metal Fuel Reactor Experiment: Quarterly Technical Report No. 1, BAW-1001, July 1, 1956 to November 15, 1956

This is the first quarterly report which summarizes the project work on the Liquid Metal Fuel Reactor Experiment. As the initial contract was not signed until November, 1956, progress within this reporting period has been limited to establishing objectives, determining what research and development will be required, and selecting preliminary design parameters.
Date: 1956-07/1956-11
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Stability of Florothene Under Exposure to Gamma Radiation (open access)

Stability of Florothene Under Exposure to Gamma Radiation

The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.
Date: July 6, 1956
Creator: Adler, K. L.
System: The UNT Digital Library
An interim report on the Lone Pine, California airborne survey (open access)

An interim report on the Lone Pine, California airborne survey

A report discussing an airborne radiometric survey of the Lone Pine, California project.
Date: July 1, 1956
Creator: Mallory, Neil S. & Richards, Arthur J.
System: The UNT Digital Library
Emission Rate of Fission Products from a Hole in the Cladding of a Reactor Fuel Element (open access)

Emission Rate of Fission Products from a Hole in the Cladding of a Reactor Fuel Element

It is assumed that when a hole appears in the cladding of a reactor fuel tube the fission products in the space between the fuel and the cladding will diffuse towards the hole. There they are swept away by the flow of steam past the hole. The process of diffusion is assumed to be governed by the ordinary diffusion equation with the boundary condition that the density of the fission products is zero at the surface of the hole. The diffusion equation is solved for the case of steady-state emission for a number of geometrical arrangements: long slit in plane surface; long slit in cylindrical surfaces circular hole in plane surface; circular hole in cylindrical surface; hole at end of cylindrical fuel rods and diffusion space of variable thickness. The time dependent solution of the diffusion equation is also found for a planar diffusion space. The effect of a temperature gradient is discussed.
Date: July 26, 1956
Creator: Helstrom, Carl W.
System: The UNT Digital Library