Analytical procedures for the plutonium Metal Fabrication Process (open access)

Analytical procedures for the plutonium Metal Fabrication Process

Report describing the results of the cupferron extraction-copper spark method in determining the impurity elements in plutonium metal. This was required the 234-5 Project analytical program.
Date: July 25, 1952
Creator: Bierlein, T. K.; Kendall, L. F. & Van Tuyl, H. H.
System: The UNT Digital Library
Analytical Procedures for the Plutonium Metal Fabrication Process (open access)

Analytical Procedures for the Plutonium Metal Fabrication Process

Report describing methods of determining trace impurities in plutonium in connection with the Metal Fabrication Process. The methods included are the cupferron extraction-copper spark method and the direct copper spark method.
Date: July 25, 1952
Creator: Bierlein, T. K.; Kendall, L. F. & Van Tuyl, H. H.
System: The UNT Digital Library
Natural Steam and Geothermal Power Generation : [bibliography] (open access)

Natural Steam and Geothermal Power Generation : [bibliography]

The following document is a bibliography containing a collection of documents discussing natural steam and geothermal power generation.
Date: July 25, 1958
Creator: Maynard, G. R.
System: The UNT Digital Library
Preparation and Properties of RAF Solutions : Low Acid TBP Flowsheets HW Number 4 and HW Number 5 (open access)

Preparation and Properties of RAF Solutions : Low Acid TBP Flowsheets HW Number 4 and HW Number 5

This report follows work with the purposes of determining the minimum amount of nitric acid required to dissolve slurries of stored metal waste, determining the stability of such metastable solutions as a function of their chemical compositions - primarily acidity - versus time and temperature, and to define a feed suitable for a low-acid TBP process flowsheet, and to indicate the range of variations in composition which can be tolerated for plant operation.
Date: July 25, 1950
Creator: Maness, R. F. & Harmon, M. K.
System: The UNT Digital Library
The Prompt Radiations in the Spontaneous Fission of Cf²⁵² (Revised) (open access)

The Prompt Radiations in the Spontaneous Fission of Cf²⁵² (Revised)

Summary: The radiations emitted in the spontaneous fission of Cf²⁵² have been studied. The results in general are in agreement with other similar measurements. An experiment is described which is expected to give the neutron energies and angular distribution in the center-of-mass system of the moving fission fragment when the analysis is completed.
Date: July 25, 1958
Creator: Bowman, H. R. & Thompson, Stanley Gerald, 1912-1976
System: The UNT Digital Library
Factors Affecting the Penta-Ether Extraction Uranium (open access)

Factors Affecting the Penta-Ether Extraction Uranium

This report discusses the contributions of the workers at Tennessee Eastman Corporation in the investigation of limiting conditions in the application of penta-ether (aka. dibutoxytetraethylene).
Date: July 25, 1947
Creator: Musser, D. F.; Krause, D. P. & Smellie, Robert H.
System: The UNT Digital Library
Neutron Leakage Through Iron (open access)

Neutron Leakage Through Iron

Neutron attenuation in the old pile shields is dependent more and more on the slowing down characteristics of the iron as the hydrogen is baked out of the masonite. For neutrons above 1 or 2 Mev, iron does a good job by inelastic scattering. However, below this energy attenuation can be done only by the gradual moderation by elastic scattering to thermal energies with subsequent capture in the iron. Since iron is heavy and thus a poor moderator, there is a good possibility that many neutrons of intermediate energy will leak out of a burned out shield. Also, iron has a large dip in its cross section at 25 Kev which might allow a large burst of neutrons at this energy to leak out. Measurements using a lucite moderator with gold foil detectors indicate a large leakage of neutrons of intermediate energy, but interpretation of these measurements is difficult. These considerations prompted an attempt to get a rough idea of the energy distribution of the leakage neutrons through pure iron using a simple qualitative theory.
Date: July 25, 1956
Creator: Wood, D. E.
System: The UNT Digital Library
Tests on a High Current R.F. Joint in Vacuum (open access)

Tests on a High Current R.F. Joint in Vacuum

An R.F. joint tester was designed to determine the relative heating and tendency toward arching at high RF current density (100 amps/linear inch) of a 12 inch diameter circular copper butt joint in vacuum with several types of inserts and at various amounts of axial loading, ranging from a very small contact pressure to one of 1400 pounds per linear inch of joint.
Date: July 25, 1951
Creator: Wharton, Charles B.
System: The UNT Digital Library
Power Distributions for Type 3 Replacement Cores for SM-1, SM-1A and PM-2A (open access)

Power Distributions for Type 3 Replacement Cores for SM-1, SM-1A and PM-2A

Abstract: The most adverse power distribution and power peaking factors have been developed for Type 3 replacement cores for SM-1, SM-1A, and PM-2A. Also included is the 37 element Type 3 core for SM-1, which is known as SM-1 Core III and is a prototype of a Type 3 core for PM-2A. The power distributions were compared with measured distributions obtained on type 3 fuel elements in SM-1, SM-1A and PM-2A core configurations. Using the measured data as a standard, correction factors were obtained and applied to the analytical predictions of the most adverse power distribution.
Date: July 25, 1962
Creator: Oggerino, J. P.
System: The UNT Digital Library
Plowshare Program : Peaceful Uses for Nuclear Explosives (open access)

Plowshare Program : Peaceful Uses for Nuclear Explosives

The concept of thermonuclear explosives as a potentially cheap and almost inexhaustible energy source for mankind's non military needs has for several years been under active consideration at the Lawrence Radiation Laboratory. Many of the proposed peaceful applications involve underground nuclear explosions, and several experiments at the AEC Nevada Test Site have provided valuable insight into the phenomenology of such explosions. Among the possible uses currently under consideration are excavation, heat production, isotope production, mining, recovery of oil from shales and tar sands, improvements of ground water supplies, and the construction of earth fill dams. In addition a program of experimental research in the laboratory and in the field is under way. Sometime in 1961 Project Gnome if approved will be conducted in New Mexico. The purpose of Gnome, a contained nuclear explosion in a salt deposit, is to study the feasibility of heat recovery and isotope production, neutron scattering experiments will also be included. Other proposed nuclear projects will involve the creation of a small harbor near Cape Thompson, Alaska as the result of an experiment designed to investigate the cratering effects of nuclear explosives; a proposal to investigate the recovery of oil from Canadian tar sands using thermonuclear …
Date: July 25, 1960
Creator: Lombard, David B.
System: The UNT Digital Library
Atmospheric Contamination Associated with Inert-Gas-Shielded, Consumable Electrode Welding (open access)

Atmospheric Contamination Associated with Inert-Gas-Shielded, Consumable Electrode Welding

Apparent excessive concentrations of atmospheric contamination which were reported to be associated with an inert-gas-shielded consumable electrode arc wielding operation were studied to evaluate the potential health hazards. A study was made of the concentrations of metal fume and gaseous products of the operation as well as the spectrum of ultraviolet radiation. Recommendations for necessary controls were made.
Date: July 25, 1955
Creator: Adley, F. E. & Gill, W. E.
System: The UNT Digital Library
Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System (open access)

Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System

This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.
Date: July 25, 1959
Creator: Craig, W. D.
System: The UNT Digital Library