Resource Type
Serial/Series Title
Atomic Energy Commission Reports
206
AEC research and development report
69
Oak Ridge National Laboratory Reports
62
University of California Radiation Laboratory Reports
60
UCRL (Series)
53
Report (U.S. Atomic Energy Commission)
52
TID
51
NYO (Series) (New York)
48
UC (Series)
35
United States Geological Survey Reports
34
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States
549 Matching Results
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Fuel Element Transient Temperature Studies
A method is presented for the analysis of transient temperatures in a homogeneous circular cylindrical fuel element in a coolant channel with no axial conduction and no heat loss to the channel wall. In addition, some results were obtained for mean fuel element temperatures in power transients for a simpler model, but accounting for details of the axial coolant temperature distribution in the unsteady state. (auth).
Date:
November 1, 1961
Creator:
Thompson, J. J.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Port Survey of the State of New York
Report of the capabilities of the state of New York to construct and service atomic propelled vessels and to handle the shipment of packaged radioactive materials, including used nuclear fuels.
Date:
November 1961
Creator:
Ebasco Services Incorporated
Object Type:
Report
System:
The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Sixth Quarter, October-December 1960
From introduction: "This is the sixth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date:
November 1961
Creator:
Pennington, R. T.
Object Type:
Report
System:
The UNT Digital Library
The Post-Irradiation Examination of a PuOâ‚‚-UOâ‚‚ Fast Reactor Fuel
From abstract: "Post-irradiation examination consisted of dimensional measurements, gamma scans, determination of fission gas release, visual examination of the fuel, measurement central voids, and metallographic examination of selected samples.
Date:
November 1961
Creator:
Gerhart, J. M.
Object Type:
Report
System:
The UNT Digital Library
A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques
From Summary: "The work described in this report is the application of this process to the recovery of uranium from highly enriched, low uranium-zirconium alloy plate-type fuels."
Date:
November 1961
Creator:
Levitz, N.; Barghusen, J.; Carls, E. & Jonke, A. A.
Object Type:
Report
System:
The UNT Digital Library
Some methods of surface analysis for the prediction of thermal resistance of metal contacts
"Equations for the heat-transfer coefficient existing at the interface of two metals in contact are discussed. The results of applying the equations (with a graphical determination of the geometric parameters) to an iron--aluminum contact are presented. A method is given for performing the graphical analysis by means of a general purpose analog computer. Data are included that were obtained by applying this method to Blanchard ground stainless steel surfaces in contact. Statistical analysis was applied to surfaces to determine the geometric properties of the contact as a function of root-mean-square roughness and method of surface preparation."
Date:
November 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Status Report on the Argonne Advanced Research Reactor
From Introduction: "This is a status report on the interim design and development for an advanced research reactor (AARR) that will produce a maximum thermal neutron flux of 5 x 10 to the fifteenth power neutrons/ (cm2) (sec). As a result, this report also contains sections covering shielding, plant layout, fuel charging, maintenance, and auxiliary facilities."
Date:
November 1961
Creator:
Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Object Type:
Report
System:
The UNT Digital Library
The Thermal Hydraulics Laboratory at Hanford
Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date:
November 1961
Creator:
Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
Object Type:
Report
System:
The UNT Digital Library
Fifth Quarterly Progress Report on Fission Product Applications Using Gaseous Beta Sources
"Rates of acetylene polymerization induced by Kr/sup 85/ in d-c fields were up to 15 times greater than those observed when no fields were imposed. Work to determine the relations between acetylene pressure, Kr/sup 85/ concentration, and the field intensity is continuing. In other activities, equipment is being designed to study the effects of megacycle electric fields on radioinduced chemical reactions."
Date:
October 31, 1961
Creator:
Graessley, William W. & Zufall, John W.
Object Type:
Report
System:
The UNT Digital Library
Final Contract Report for September 1, 1959 to August 31, 1960 .
"As presented in the original proposal the project consisted essentially of three parts: Phase I, Development and refinement of a radiochemical flow counting technique for the study of kinetics of reactions in solution ; Phase II, The application of this technique to the detailed study of the mechanism of solvolysis of sulfonium salts in mixed solvents ; Phase II, The further application of this kinetic technique, as a longer term aim, to other reacting systems of biochemical or other interest. This report covers the work of the contractual period 1 Sept. 1959 to 31 Aug. 1960."
Date:
October 31, 1961
Creator:
Hyne, James B.; Abrell, J. W.; Gurst, J. E. & Jacobson, Ada L.
Object Type:
Report
System:
The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1961
Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date:
October 31, 1961
Creator:
Oak Ridge National Laboratory. Health Physics Division.
Object Type:
Report
System:
The UNT Digital Library
Synthesis of Semiconductor Materials by Radiation Induced Reactions
""Progress is reported on: design of a continuous flow system for the irradiation of silane using a Cos5 source; pile irradiation of silane samples at elevated temperatures; investigation of materials other than silane, including nonsilicon compounds as well as those containing the silyl group; modification of the existing vacuum system for handling larger quantities of silane as well as increasing the accuracy of the pressure measurements; and use of an electric discharge for the decomposition of silane. Studies were continued on the radiation- and thermalinduced decomposition of sikane at 325 and 350 deg C. A preliminary value of G= 33 was obtained for silane."
Date:
October 31, 1961
Creator:
{{{name}}} & Goldman, Richard
Object Type:
Report
System:
The UNT Digital Library
Synthesis of Semiconductor Materials by Radiation Induced Reations
"Progress is reported on: design of a continuous flow system for the irradiation of silane using a Cos5 source; pile irradiation of silane samples at elevated temperatures; investigation of materials other than silane, including nonsilicon compounds as well as those containing the silyl group; modification of the existing vacuum system for handling larger quantities of silane as well as increasing the accuracy of the pressure measurements; and use of an electric discharge for the decomposition of silane. The work performed during the period of this report consisted of the following: 1. Preparation of samples of trichlorosilane and hydrogen and subsequent thermal and irradiation studies, and analysis of these samples. 2. Preparation of mixed samples of silane and argon and subsequent thermal and irradiation studies and and analysis. 3. Outlining of future investigations to be conducted on this project."
Date:
October 31, 1961
Creator:
Held, Kelman & Goldman, Richard
Object Type:
Report
System:
The UNT Digital Library
Corrosion and Activity Transfer in the SRE Primary Sodium System
Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date:
October 30, 1961
Creator:
Johnson, H. E.
Object Type:
Report
System:
The UNT Digital Library
A Recoil Study Of The Reaction C12(p,pn)C11 [formula]
Recoil ranges of C11 from the reaction C12(p,pn)C11 are presented for incident proton energies from 0.25 to 6.2 Gev. From these data it is concluded that a neutron evaporation mechanism cannot be the major mechanism. The result for incident energies of 3 and 6.2 Gev are consistent with a fast reaction consisting of a single inelastic nucleon-nucleon collision. Assuming this mechanism, an average kinetic energy of 19 Mev can be deduced for the struck neutron (before the collision) in the C12 nucleus.
Date:
October 24, 1961
Creator:
Singh, Sarjant & Alexander, John M.
Object Type:
Report
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps
Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Internal Heat Generation on Pot Calcination Rates for Radioactive Wastes
Review of methods by which the radial deposition mechanism was determined in experiments with simulated waste solutions are briefly reviewed.
Date:
October 23, 1961
Creator:
Perona, J. J.
Object Type:
Report
System:
The UNT Digital Library
Low Frequency Amplifier IH-130-1
A tranistorized d.c. coupled amplifier having very good gain stability, as well as very low drift of the output d.c. level, has been designed. Low frequency input signals with an amplitude of .04 to 2 volts peak-to-peak, approximately, coming from a low impedance source (voice soil of a speaker system) are amplified to an approximate peak-to-peak amplitude of 4 volts. The output is intended to drive a load of the order of 100 kohm.
Date:
October 23, 1961
Creator:
Llacer, Jorge
Object Type:
Report
System:
The UNT Digital Library
Boiling of Freon-114 in a Three-Foot Straight Tube Evaporator
Introduction: this report covers two series of tests run on a Freon evaporator containing a vertical copper tube having an outside diameter of 7/8 of an inch, heated externally for a length of 35 inches by steam condensing in a concentric jacket.
Date:
October 19, 1961
Creator:
Allen, Charles F.
Object Type:
Report
System:
The UNT Digital Library
Criteria for Evaluating Hazards Involved in Proposed Tests On and/or Modifications To the SM-1
Abstract: This technical report elucidates principles of hazards evaluation. The concept of hazards potential is introduced and utilized to show how a reactor system perturbation will influence its nuclear safety. Literature relating to reactor safety is referenced to provide the sources of information required for hazards analysis and show how they influence a hazards evaluation. A checklist of items which should be considered in evaluating a change, test, or modification is presented.
Date:
October 18, 1961
Creator:
Scoles, J. F.
Object Type:
Report
System:
The UNT Digital Library
Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators
"A brief examination of the post irradiation grafting of machine irradiated polyethylene film with acrylic acid monomer was made. Evidence of postgrafting was detected in samples that had been irradiated to a total dose of 10 Mrads at a dose rate of 0.01 Mrad/sec. and then exposed to a 25% purified acrylic acid solution in benzene for periods of 1 to 4 days."
Date:
October 17, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library