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Proceedings of the Symposium on the Solidification and Long-Term Storage of Highly Radioactive Wastes: February 14-18, 1966, Richland, Washington
Symposium proceedings regarding long-term storage of highly radioactive wastes resulting from nuclear reactors.
Date:
November 1966
Creator:
Regan, W. H.
System:
The UNT Digital Library
Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions
Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.
Date:
September 28, 1962
Creator:
Stein, P. E.
System:
The UNT Digital Library
Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant
Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
Date:
October 5, 1962
Creator:
Miskell, R. V.
System:
The UNT Digital Library
Automatic Mass Spectrometer for Isotopic Analysis of Lithium
Report discussing an improvement program on lithium mass spectrometers.
Date:
March 15, 1962
Creator:
McBryde, W. T. & Gammon, E. F.
System:
The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses
Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
Date:
May 21, 1962
Creator:
McMurray, C. S.
System:
The UNT Digital Library
The Application of Data Processing Techniques to a Maintenance Work Control Program
Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.
Date:
December 18, 1963
Creator:
Westbrook, J. D.
System:
The UNT Digital Library
The Cold Pressing of Sinterable UOâ‚‚
The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date:
March 27, 1961
Creator:
Levey, R. P., Jr.
System:
The UNT Digital Library
Transistorized Pulse Counting Equipment
This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
Date:
July 26, 1960
Creator:
Henry, John J.
System:
The UNT Digital Library
The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements
The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
Date:
November 1, 1961
Creator:
Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.
System:
The UNT Digital Library
An Investigation of a "Dynamic" Theory for Mass Transfer
A new theory is proposed to evaluate individual mass-transfer coefficients without actual experiment.
Date:
July 18, 1960
Creator:
Schappel, Richard B.
System:
The UNT Digital Library
Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report
This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
Date:
September 12, 1958
Creator:
Patton, F. S.; Bailey, J. C.; Callihan, A. D.; Googin, J. M.; Jasny, G. R.; McAlduff, H. J. et al.
System:
The UNT Digital Library
Portable Mercury Vapor Detector
From abstract: "This report describes a functional mercury vapor detector which is a portable, self-contained, survey instrument, and had a minimum range from zero to two-tenths milligram of mercury per cubic meter of air."
Date:
March 14, 1958
Creator:
McMurray, C. S. & Redmond, J. W.
System:
The UNT Digital Library
Uranium Concentration Meter
From abstract; "Two basic instruments were developed for determining the concentration of uranium in solutions. Both instruments detect the gamma activity present in a sample solution, and interpret this analysis into direct presentation as parts per million."
Date:
September 24, 1956
Creator:
Arnett, Orville
System:
The UNT Digital Library
A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals
Abstract: "This report describes a flame photometric system which continuously monitors a process water stream for ppm quantities of alkali metals, and automatically diverts the stream when the contamination exceeds a pre-determined level."
Date:
June 20, 1955
Creator:
Been, Julian F.
System:
The UNT Digital Library
Production of Zirconium at Y-12
Abstract: "A general description is given of the permanent zirconium plant at Y-12. Equipment is described and materials of construction are listed. Photographs illustrating principal equipment and reduced construction drawings are also presented. Operating conditions and costs information are listed."
Date:
November 17, 1955
Creator:
Ramsey, J. W. & Whitson, W. K., Jr.
System:
The UNT Digital Library
Status Report and Plant Proposals for Zirconium Purification
From abstract: "This report contains a summary of the latest improvements in zirconium purification as developed by the Y-12 research, pilot plant, production, and engineering groups, all of whom have been generously cooperating in this project."
Date:
November 18, 1955
Creator:
Leaders, W. M.
System:
The UNT Digital Library
Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant
Abstract: A re-evaluation of the cost of producing essentially hafnium free zirconium as zirconium oxide at a rate of 150,000-200,000 pounds zirconium per year by solvent extraction of the metal thiocyanates in a permanent plant has been made. Using part of the present temporary facilities, the cost, with five year amortization of the plant, will be $3.15 per pound zirconium. A by-product of the mixed oxides of hafnium and zirconium, having at least fifty percent hafnium and perhaps as high as ninety percent hafnium, can be made available with little additional cost.
Date:
November 17, 1955
Creator:
Googin, J. M. & Strasser, G. A.
System:
The UNT Digital Library
Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report
Abstract: Use of the mixer-settler apparatus as a rapid means of determining improved conditions for plant operation is described including the experimental details. The preparation of highly purified samples of both zirconium oxide and hafnium oxide is discussed. (This document is concerned almost entirely with explorations of small scale continuous systems. Another document dealing with this general problem using small scale batch operations is being published simultaneously. It should prove of advantage to the reader to study this companion report, Document Y-611, by Barton, Overholser, and Grimes, to obtain a complete picture of the available information.).
Date:
November 17, 1955
Creator:
Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
System:
The UNT Digital Library
The Alco Products Inc. Criticality Facility : Description and Operation
The Alco Products Criticality Facility, site location, and operating procedures are described in detail, including the handling of fissionable material and the operating procedures for the safe performance of critical experiments.
Date:
July 16, 1958
Creator:
Noaks, John W.
System:
The UNT Digital Library
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960
Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date:
February 3, 1961
Creator:
Oak Ridge National Laboratory. Instrumentation and Controls Division.
System:
The UNT Digital Library
Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.
Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.
Date:
May 27, 1960
Creator:
Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
System:
The UNT Digital Library
Scale "Up or Down" Analysis for Prototype Test
Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date:
May 1, 1960
Creator:
Alco Products (Firm).
System:
The UNT Digital Library
Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I
Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II and SM-1A Core I contain nearly identical B-10 loading of 17.79 grams, compared to the best estimate of 15.75 grams for SM-1 Core I. The available data indicates that all three cores possess similar nuclear characteristics.
Date:
October 5, 1960
Creator:
Paluszkiewicz, S.
System:
The UNT Digital Library
Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3
Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.
Date:
February 28, 1961
Creator:
Hasse, Robert A. & Zegger, John L.
System:
The UNT Digital Library