Liquid Reactor Fuels: Bismuth-Uranium System (open access)

Liquid Reactor Fuels: Bismuth-Uranium System

Technical report about the liquidus curve for the nuclear reactors bismuth-uranium system and the need for a suitable container for this fuel.
Date: September 15, 1950
Creator: Bareis, D. W.
System: The UNT Digital Library
Unit for Continuous Separation of U233 From Thorium Fluoride (open access)

Unit for Continuous Separation of U233 From Thorium Fluoride

Technical report outlining a preliminary design for carrying out the process of producing U233 from Th232.
Date: September 15, 1950
Creator: Dwyer, O. E.
System: The UNT Digital Library
OMR Control-Safety Rod Component Development Tests (open access)

OMR Control-Safety Rod Component Development Tests

Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date: September 15, 1959
Creator: Howell, J. D.
System: The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System (open access)

Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System

Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date: September 15, 1961
Creator: Schlein, H.
System: The UNT Digital Library
A Multichannel Digital Recording System (open access)

A Multichannel Digital Recording System

Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date: September 15, 1960
Creator: Truitt, R. W.
System: The UNT Digital Library
Carbide Fuels in Fast Reactors (open access)

Carbide Fuels in Fast Reactors

Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
System: The UNT Digital Library
A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power (open access)

A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power

"A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 degrees F and is returned at 420 degrees F. Steam conditions at the turbine throttle are 600 psig and 825 degrees F. Cost of the complete reactor power plant, consisting of the three reactors, and on 150-megawatt turbogenerator, is estimated to be approximately $43,165,000."
Date: September 15, 1954
Creator: Weisner, Edward F.
System: The UNT Digital Library
Uranium Oxide Slurry Pumping Experiments (open access)

Uranium Oxide Slurry Pumping Experiments

Abstract: Experiments on colloid milling and pumping show that uranium trioxide, when carefully dehydrated, can be dispersed in water to form a relatively stable slurry, suitable for a homogeneous slurry pile. At temperatures considerably below those of anticipated pile operation particle size growth occurs attended by increase in settling rate and decrease in viscosity. Theses properties of the slurries may be strongly affected by impurities present as well as by special operating conditions.
Date: September 15, 1944
Creator: Brandt, R. & Dean, G. R.
System: The UNT Digital Library
Stress and Elevated Temperature Fatigue Characteristics of Large Bellows (open access)

Stress and Elevated Temperature Fatigue Characteristics of Large Bellows

From abstract: Charts in this report show axial stress distribution over exterior bellows surfaces induced by bellows axial deflection, and by internal pressurization. The influence of root rings on stress distribution is presented graphically.
Date: September 15, 1964
Creator: Winborne, R. A.
System: The UNT Digital Library
Pressurized Loop membrane Demineralizer Tests : Final Report [for] January-June 1953 (open access)

Pressurized Loop membrane Demineralizer Tests : Final Report [for] January-June 1953

A membrane demineralizer has been tested in a pressurized loop. The loop water resistivity was maintained in the 1-2 megohm range by ionized solid transfer in the demineralizer. The size and power requirement of the unit tested per gpm flow through the unit, were 2.3 cu ft and 100 watts. In view of the fact that present designed could reduce the size and required maintenance, further studies may be warranted.
Date: September 15, 1954
Creator: Rosenberg, N. W.
System: The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964 (open access)

Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964

From introduction: This report provides industry, plant operators, and the scientific community with information covering the results of the performance analysis.
Date: September 15, 1964
Creator: Darley, D. K.
System: The UNT Digital Library
The Catalytic Decomposition of Hydrogen Peroxide by Iron Salts in Acid Solution (open access)

The Catalytic Decomposition of Hydrogen Peroxide by Iron Salts in Acid Solution

The following document discusses general theories of hydrogen peroxide decomposition.
Date: September 15, 1945
Creator: Pomeroy, J. H.; Grieger, P. F. & Gates, J. W.
System: The UNT Digital Library
Equilibrium Configuration of a Plasma in the Guiding Center Limit (open access)

Equilibrium Configuration of a Plasma in the Guiding Center Limit

"We compute the equilibrium configuration of a collision-free plasma contained in an axially symmetric magnetic field. The plasma is characterized by a non-scalar pressure tensor which is obtained from a microscopic distribution function in a form suggested b the guiding center approximation. The solution is calculated in the limit where the ratio of the width to the length of the plasma region and the ratio of the gas to the magnetic pressure are both small. Boundary values at the midplane as well as the shape of the plasma appear as arbitrary parameters in the solution. We give the solution to a corresponding scalar pressure problem for comparison."
Date: September 15, 1960
Creator: Oppenheim, Alan
System: The UNT Digital Library
Evaluation of Countermeasure System Components and Operational Procedures (open access)

Evaluation of Countermeasure System Components and Operational Procedures

"The objective of project 32.3 was to evaluate some operational characteristics of a radiological shelter and to determine values for some countermeasures-system parameters."
Date: September 15, 1959
Creator: Strope, W. E.
System: The UNT Digital Library
Response of Dual-Purpose Reinforced-Concrete Mass Shelter (open access)

Response of Dual-Purpose Reinforced-Concrete Mass Shelter

From introduction: The primary objective of Project 30.2 was to evaluate the protection afforded by a reinforced-concrete dual-purpose underground parking garage and personnel shelter against effects of a nuclear detonation.
Date: September 15, 1962
Creator: Cohen, Edward; Laing, E. & Bottenhofer, A.
System: The UNT Digital Library
Second Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utiiization (open access)

Second Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utiiization

The objective of the study which is being carried out under contract AT(30-1)-2477 is the exploration of all aspects of research in water resources and supply to determine the potential for using radioisotope technology in this research. Problem areas in the application of tracers in this research are being investigated through the evaluation of past experimentation with radioisotopic techniques and through discussions with those who are active in this work. A series of suggestions relating to these techniques will de drawn up to indicate which techniques should be developed further in order that more extensive applications may be found for them.
Date: September 15, 1960
Creator: Isotopes Incorporated
System: The UNT Digital Library
The Effect of X Irradiation in Oxygen and in Hydrogen at Normal and Positive Pressures on Chromosome Aberration Frequency in Tradescantia Microspores (open access)

The Effect of X Irradiation in Oxygen and in Hydrogen at Normal and Positive Pressures on Chromosome Aberration Frequency in Tradescantia Microspores

Effect of x irradiation in oxygen and in hydrogen on chromosome aberration frequency in tradescantia microspores.
Date: September 15, 1950
Creator: Giles, Norman H., Jr. & Beatty, Alvin V.
System: The UNT Digital Library
Standard Practices for Design of MTR and ETR Safety Circuits (open access)

Standard Practices for Design of MTR and ETR Safety Circuits

Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date: September 15, 1957
Creator: Jones, L. H.
System: The UNT Digital Library
The Distribution of Tracer Plutonium and Fission Products Between Molten Uranium and Solid Uranium Oxide, Carbide, and Nitride (open access)

The Distribution of Tracer Plutonium and Fission Products Between Molten Uranium and Solid Uranium Oxide, Carbide, and Nitride

"A study has been made of the distribution of tracer fission products and plutonium between small samples of molten uranium and solid uranium oxide, carbine, and nitride. The distribution showed the same behavior i general for all three materials: 1. The rare earth elements, Cs, Ba, and Sr were extracted primarily into the solid scrub phase. 2. Zirconium and Nb partially concentrated in the scrub phase. 3. Plutonium, Mo, and Ru tended to remain completely in the metal phase. The distribution of activities agreed with trends predicted from the thermodynamic data. Uranium oxide appeared to be the most desirable scrub material for removing large amounts of fission products from the uranium while leaving beind the Pu. In addition the uranium metal was not severley contaminated by dissolved oxide."
Date: September 15, 1954
Creator: Keneshea, F. J.; Saul, A. M. & Young, C. Y.
System: The UNT Digital Library
Improved Method for Numerically Solving Multi-Group Reactor Equations (open access)

Improved Method for Numerically Solving Multi-Group Reactor Equations

"A method for solving multi-group reactor equations which arise in the diffusion approximation is outlined. Considerable work has been done on this problem at KAPL and ORNL. Their approach is to replace the differential equations by difference equations. Complications arise in this method where more than one slowing down medium is present since the fluxes are discontinuous at the interfaces. The primary purpose of this article is to develop an exact integral expression for the neutron flux which automatically satisfies the boundary conditions. An iterative method for obtaining the fluxes and critical neutron multiplication ratio based upon the above-mentioned integral expression is given. The only approximation used in obtaining the fluxes, in addition to the use of multi-group diffusion theory as the basic model, is the use of numerical integration to evaluate the analytic expression. The equations for a two region, two group spherical reactor are given in a form suitable for machine programing. The extension to more than two regions is also considered.
Date: September 15, 1954
Creator: Lehman, G. W.
System: The UNT Digital Library
Interpretation of Westwood, New Jersey Rainfall Data (open access)

Interpretation of Westwood, New Jersey Rainfall Data

"Progress is reported in an evaluation of fission product concentration in rain as a function of time, location, and meteorological setting. Data on rainfall collected at Westwood, N. J., were analyzed for information on the mechanisms of fallout deposition, seasonal variations in fallout, the stratospheric residence time of W/sup 185/ resulting from Operation Hardtack, and the accuracy of pot samplers for sample collection. Data from other collection stations were also analyzed for consistency with Westwood data."
Date: September 15, 1959
Creator: unknown
System: The UNT Digital Library
A Preliminary Study of the Potential to Kinetic Energy Conversion Process in the Stratosphere (open access)

A Preliminary Study of the Potential to Kinetic Energy Conversion Process in the Stratosphere

The potential to kinetic energy conversion process in the lower stratosphere is evaluated using adiabatically derived vertical velocities for the North American region for a five-day period. Preliminary results suggest the possibility that on the average the kinetic energy of stratospheric motions may not result from a conversion of potential energy within the stratosphere. The further implication is that stratospheric motions are mechanically driven by the motions in the adjacent layers of the atmosphere.
Date: September 15, 1959
Creator: White, Robert M., 1923-2015 & Nolan, George F.
System: The UNT Digital Library