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1024 Channel Time-of-Flight Analyzer for MTR Fast Chopper - Operating Manual

Description: Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.
Date: March 11, 1959
Creator: Petree, F. L.
Partner: UNT Libraries Government Documents Department
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Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho, Part 3: Hydrology and Water Resources

Description: This report describes the hydrology and evaluates the water resources of the ERTS, sets these in their regional perspective, and forecasts conditions and effects during future years.
Date: 1959
Creator: Nace, Raymond L.; Deutsch, Morris; Voegeli, Paul T.; Steward, J. W.; Walton, William Clarence; Fowler, K. H. et al.
Partner: UNT Libraries Government Documents Department
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Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

Description: The purpose of this document is to present criteria for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the Advanced Test Reactor. This facility is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions.
Date: July 1962
Creator: Babcock & Wilcox Company. Atomic Energy Division.
Partner: UNT Libraries Government Documents Department
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Geography, Geology, and Water Resources of the National Reactor Testing Station, Idaho : Part 2, Geography and Geology

Description: Geologic factors in the physical environment of the National Reactor Testing Station control the amount and availability of the water supply, the methods and efficiency of obtaining water, and the behavior of waste materials that are disposed on the ground or beneath the land surface.
Date: 1956
Creator: Nace, R. L.; Deutsch, Morris & Voegeli, P. T.
Partner: UNT Libraries Government Documents Department
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Materials Testing Reactor-Engineering Test Reactor Technical Branches Quarterly Report: October 1 - December 31, 1963

Description: From summary: "Reactor fuel material consisting of U3Si particles embedded in an aluminum matrix have been examined with an electron microprobe to determine reaction between fuel particles and matrix. Partial reaction was observed with no observable tendency for the uranium or silicon to diffuse outward into the matrix.
Date: May 1964
Creator: Phillips Petroleum Company
Partner: UNT Libraries Government Documents Department
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Rice Lake Quadrangle, Wisconsin

Description: The following report presents the hydrogeochemical and stream sediment and aerial radiometric reconnaissance survey data that were evaluated in uranium resources of the Rice Lake Quadrangle, Wisconsin.
Date: January 1981
Creator: Routledge, R. E.; Parrish, I. S. & Leigh, O. E.
Location: None
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

Description: From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Description: 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.
Partner: UNT Libraries Government Documents Department
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The ML-1 Design Report

Description: From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date: May 16, 1960
Creator: Linenberger, G. A.
Partner: UNT Libraries Government Documents Department
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In-Pile Tests of GCRE-IB Prototype Fuel Elements: Interim Report, 1958-1959

Description: Interim report for the Army Gas-Cooled Reactor Systems Program, discussing various tests in a project to "develop and evaluate a ceramic-core, pin-type fuel element" (p. 1).
Date: December 1960
Creator: Watanabe, H. T.; Janne, J. E. & Wilson, W. D.
Partner: UNT Libraries Government Documents Department
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Transportability Studies : ML-1 Nuclear Power Plant

Description: Report that discusses programs to determine the transportability of the ML-1 nuclear power plant via railroad, tractor-trailer, and aircraft.
Date: April 1960
Creator: Blakley, J. W.; Alcorn, J. S.; Del Valle, L. G.; Healy, P. W.; Moran, D. H. & Scott, W. S.
Partner: UNT Libraries Government Documents Department
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High-Temperature Irradiation of UO₂-BeO Bodies

Description: From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."
Date: January 1963
Creator: Titus, G. W. & Saling, J. H.
Partner: UNT Libraries Government Documents Department
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In-Pile Test of Prototype ML-1 Fuel Elements

Description: Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
Date: June 1964
Creator: Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.
Partner: UNT Libraries Government Documents Department
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Gamma-Ray Spectrometry of Neutron-Deficient Isotopes: Annual Progress Report, March 1964

Description: From abstract: "The objective of this program is to produce a set of pulse-height spectra representing the response of a standard gamma-ray scintillation spectrometer to radiations emitted in the decay of neutron-deficient nuclides."
Date: March 27, 1964
Creator: Heath, R. L. & Cline, J. E.
Partner: UNT Libraries Government Documents Department
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STEP Project Quarterly Technical Report: January-June 1964

Description: Report regarding the Safety Test Engineering Program (STEP), the transient and destructive testing of the aerospace SNAP 10A/2 reactor, and the evaluation of the results of these tests.
Date: June 1965
Creator: U.S. Atomic Energy Commission. Idaho Operations Office.
Partner: UNT Libraries Government Documents Department
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Hydrology of Subsurface Waste Disposal, National Reactor Testing Station, Idaho : Annual Progress Report, 1963

Description: From introduction: "The present report indicates additional preliminary progress in the interpretation of the geology of the area on the basis of preliminary gravity and magnetic surveys and sketches the progress made in operational phases of the study of the hydrology of waste disposal."
Date: May 1964
Creator: Morris, D. A.
Partner: UNT Libraries Government Documents Department
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Television System Study for Accident Recovery : Phase I

Description: From abstract: "A previous study of equipment necessary for clean-up following a nuclear accident indicated a need for a portable television system capable of operating in hazardous environments during recovery operations. A system to accomplish this is described and justified in this study."
Date: April 1966
Creator: Talpis, N. A. & Burge, D. L.
Partner: UNT Libraries Government Documents Department
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EOCR Control Rod and Driver Fuel Hydraulic Tests

Description: Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
Partner: UNT Libraries Government Documents Department
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The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results

Description: 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.
Partner: UNT Libraries Government Documents Department
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