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6144-Channel Time-of-Flight Analyzer
Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date:
September 1964
Creator:
Walker, R. A. & Russell, J. T.
System:
The UNT Digital Library
An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2
Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
Date:
June 2, 1958
Creator:
Spear, W. G.
System:
The UNT Digital Library
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel
Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Date:
July 1963
Creator:
Jackson, C. N., Jr.
System:
The UNT Digital Library
Analog Computer Simulation of a Pulsed Extraction Column
Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Date:
September 1964
Creator:
Benham, R. D. & Wilburn, N. P.
System:
The UNT Digital Library
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model
Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date:
September 1, 1964
Creator:
Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
System:
The UNT Digital Library
An Automatic Analyzing Monitor for Reactor Effluent Cooling Water
From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
Date:
May 1, 1959
Creator:
Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.
System:
The UNT Digital Library
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water
Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
Date:
April 1963
Creator:
Rieck, H. G. 1922-
System:
The UNT Digital Library
Beta-Gamma Dose Rates from U232 in U233
This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
Date:
April 1964
Creator:
Owen, F. E.
System:
The UNT Digital Library
Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements
Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Date:
August 1962
Creator:
Hanthorn, H. E.
System:
The UNT Digital Library
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C
Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date:
August 12, 1960
Creator:
Wilburn, N. P.
System:
The UNT Digital Library
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment
Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Date:
May 1963
Creator:
Larrick, A. P.
System:
The UNT Digital Library
Critical Mass Studies of Plutonium Solutions
Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date:
February 15, 1960
Creator:
Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
System:
The UNT Digital Library
Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks
Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
Date:
May 15, 1958
Creator:
Morrow, G. W.
System:
The UNT Digital Library
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium
Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3).
Date:
October 1963
Creator:
Wheelwright, E. J. (Earl J.) & Roberts, F. P.
System:
The UNT Digital Library
A Device for Recording Fuel Element Dimension on Punched Paper Tape
Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii).
Date:
December 1962
Creator:
Driver, G. E.
System:
The UNT Digital Library
Dissolution of Power Reactor Fuel Cores
Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Date:
August 26, 1960
Creator:
Blaine, H. T.
System:
The UNT Digital Library
Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI
Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
Date:
October 20, 1959
Creator:
Moore, R. H. & Lyon, W. L.
System:
The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date:
June 1961
Creator:
Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
System:
The UNT Digital Library
Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor
Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Date:
December 9, 1963
Creator:
Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
System:
The UNT Digital Library
The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel
Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2).
Date:
October 1964
Creator:
Silker, W. B. & Thomas, C. W.
System:
The UNT Digital Library
The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete
Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.
Date:
December 11, 1958
Creator:
Wood, D. E.
System:
The UNT Digital Library
Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1
Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
Date:
February 1961
Creator:
Pessl, H. J.
System:
The UNT Digital Library
Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1
Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.
Date:
December 1962
Creator:
Defferdin, L. J.
System:
The UNT Digital Library
Factors Affecting Fluidization of Uranium Trioxide Powders
Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
Date:
March 1, 1958
Creator:
Johnson, B. M.
System:
The UNT Digital Library