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101 Matching Results
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Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office
Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date:
April 1, 1958
Creator:
ACF Industries Incorporated. Nuclear Products - ERCO Division.
System:
The UNT Digital Library
Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office
Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).
Date:
April 1, 1958
Creator:
Kaiser Engineers
System:
The UNT Digital Library
Standard Practices for Design of MTR and ETR Safety Circuits
Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date:
September 15, 1957
Creator:
Jones, L. H.
System:
The UNT Digital Library
Supplement to Standard Practices for Design of MTR and ETR Safety Circuits
Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).
Date:
November 21, 1958
Creator:
Jones, L. H.
System:
The UNT Digital Library
Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO
Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date:
August 23, 1956
Creator:
Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
System:
The UNT Digital Library
Startup Operation of a Production Facility for Separating Barium-140 from MTR Fuel
Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).
Date:
September 1, 1957
Creator:
Legler, Billy Mason; Fairbourne, S. F.; Kelly, P. N. & Robinson, R. A.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961
Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.
Date:
August 10, 1961
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962
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:
August 17, 1962
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station
Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.
Date:
April 28, 1961
Creator:
Schneider, H.; Fletcher, R. D.; Codding, J. W.; Bearden, R. G.; Erickson, E. E.; Horn, S. J. et al.
System:
The UNT Digital Library
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant
Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
Date:
April 27, 1962
Creator:
Burn, P.
System:
The UNT Digital Library
Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels
Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.
Date:
June 20, 1962
Creator:
Chamberlain, H. V.
System:
The UNT Digital Library
Critical Path Scheduling of ETR and MTR Reactor Shutdowns
Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date:
January 10, 1962
Creator:
Jacobs, R. T. & Myers, L. L.
System:
The UNT Digital Library
Unitized Microfilm System for Engineering Drawings of Idaho Operations Office, USAEC and Its Contractors
Report that describes an engineering drawing microfilm system that was developed for the United States Atomic Energy Commission's Idaho Operations Office and its contractors at the National Reactor Testing Station.
Date:
April 16, 1962
Creator:
Masterson, Richard G.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959
Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date:
May 25, 1959
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
November 15, 1963
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
February 15, 1960
Creator:
Aerojet-General Corporation
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: July 1 - December 31, 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:
February 22, 1961
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Oak Ridge Site Report 30,000 KiloWatt Prototype Partially Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant
From introduction: "This report describes the selected site for a prototype nuclear plant, the reactor safety aspects for the site, the modified design of the plant, and estimate of the design and construction cost."
Date:
March 1959
Creator:
Kaiser Engineers
System:
The UNT Digital Library
Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office
Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
Date:
March 1959
Creator:
ACF Industries Incorporated. Nuclear Products - ERCO Division.
System:
The UNT Digital Library
Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor
From introduction: "Report summarizing all work completed during the preparation of design criteria for thermal flux loop."
Date:
March 1963
Creator:
Ebasco Services Incorporated
System:
The UNT Digital Library
Advanced Test Reactor Turbo Report
From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Date:
January 1964
Creator:
Turner, Robert A.
System:
The UNT Digital Library
Advanced Test Reactor Servo Regulator Rod Test Program
From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Date:
February 1964
Creator:
Pickett, R. T., III
System:
The UNT Digital Library
ICPP Waste Calcining Facility : Safety Analysis Report
Report documenting a study "made of the radiological hazards associated with operation of the ICPP Waste Calcination Facility" and contains "[d]etails of the safety analysis and extensive information on the process, equipment, and operation procedures" (p. iii). Each section has its own pagination.
Date:
December 1, 1963
Creator:
Lakey, L. T. & Bower, J. R.
System:
The UNT Digital Library