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Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1964 - June 1, 1964
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
July 1, 1964
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1960 - June 1, 1960
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
July 1, 1960
Creator:
Hardy, Edward P., Jr.; Klein, Stanley & Rivera, Joseph
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1961 - June 1, 1961
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
July 1, 1961
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1962 - June 1, 1962
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
July 1, 1962
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle
Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).
Date:
July 1963
Creator:
Vogrin, Joseph A., Jr.
System:
The UNT Digital Library
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date:
July 1960
Creator:
Bullinger, C. F. & Harrer, J. M.
System:
The UNT Digital Library
Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate
Report issued by the Argonne National Laboratory discussing irradiation tests of an aluminum alloy-clad, aluminum-uranium alloy fuel plate. As stated in the introduction, "calculations were made to determine the lowest possible pressure which would allow the maximum possible local boiling on the plate and still assure a margin of safety against burnout" (p. 9). This report includes tables, illustrations, and photographs.
Date:
July 1960
Creator:
Gavin, A. P. & Crothers, C. C.
System:
The UNT Digital Library
Performance Characteristics of a Liquid Metal MHD Generator
Report issued by the Argonne National Laboratory discussing the performance of magnetohydrodynamic generators. As stated in the abstract, "an experimental study was made of the performance characteristics of a liquid metal MHD generator utilizing single-phase sodium-potassium and two-phase sodium-potassium-nitrogen fluids. The purpose of this study was to compare the generator performance with theory for single-phase flow and to determine the effects of the introduction of the gaseous phase on the generator output and efficiency" (p. 9). This report includes tables, illustrations, and photographs.
Date:
July 1964
Creator:
Petrick, Michael & Lee, Kung-You
System:
The UNT Digital Library
Scintillation Spectrometry : Gamma-Ray Spectrum Catalogue
Report presenting a collection of gamma spectra containing samples of the response of NaI(TI) scintillation detectors to a large number of the more frequently encountered radioactive nuclides.
Date:
July 1, 1957
Creator:
Heath, R. L.
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date:
July 1964
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
July 31, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Date:
July 31, 1959
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Fuel Core Tester - UT-2
Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date:
July 18, 1960
Creator:
Frederick, C. L. & Waldkoetter, G. L.
System:
The UNT Digital Library
Hanford Controlled Potential Coulometer
Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date:
July 11, 1960
Creator:
Connally, R. E. & Scott, F. A.
System:
The UNT Digital Library
The RBU Reactor-Burnup Code: Formulation and Operation Procedures
Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date:
July 1961
Creator:
Triplett, J. R.; Merrill, E. T. & Burr, J. R.
System:
The UNT Digital Library
Liquid Metal Reactor Experiment Preliminary Hazards Evaluation, July 1957
Report containing descriptions of the Liquid Metal Fuel Reactor Experiment's reactor, containment, and plant design. Includes analyses of associated environmental hazards.
Date:
July 1957
Creator:
Babcock & Wilcox Company
System:
The UNT Digital Library
The Hanford Isotopes Production Plant Engineering Study
Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Date:
July 1963
Creator:
La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.
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
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes
Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date:
July 30, 1963
Creator:
Pessl, H. J.
System:
The UNT Digital Library
Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study
Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste
Date:
July 1964
Creator:
Godfrey, W. L. & Benham, R. D.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1963
Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
July 23, 1963
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)
Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date:
July 2, 1959
Creator:
Nakazato, S.; Williams, P. M. & Wilson, W. D.
System:
The UNT Digital Library
The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results
From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date:
July 12, 1963
Creator:
Zelezny, W. F.
System:
The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation
Engineering test reactor design and operation.
Date:
July 1964
Creator:
unknown
System:
The UNT Digital Library