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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
Design Bases for ICPP Waste Calcination Facility
Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
Date:
January 16, 1959
Creator:
MacQueen, D. K. & Stevens, J. I.
System:
The UNT Digital Library
Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor
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.
System:
The UNT Digital Library
The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS
Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date:
September 8, 1961
Creator:
Porter, E. H.
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
Design of a Pilot Plant Facility for Radioactive Demonstration of the Pot Calcination Process
Report regarding the process development work at the Oak Ridge National Laboratory, including project objectives, design considerations, descriptions of equipment, and estimated costs.
Date:
December 14, 1962
Creator:
Wheeler, B. R. & Buckham, James Andrew
System:
The UNT Digital Library
Determination of Burnout Limits of Polyphenyl Coolants : Summary Report
Report documenting an investigation undertaken "to establish the burnout limits of a polyphenyl mixture (...), diphenyl, Santowax R, and monoisopropyl-biphanyl for various pressures, fluid velocities, and fluid temperatures" (p. 7).
Date:
February 14, 1958
Creator:
Core, T. C. & Sato, K.
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
EDP Procedures in Technical Library Operations
Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date:
July 30, 1963
Creator:
Griffin, Hillis L.
System:
The UNT Digital Library
An Engineering Test Program to Investigate a Loss of Coolant Accident
From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."
Date:
October 1964
Creator:
Wilson, T. R.; Hauge, O. M.; Matheney, G. B. & Homer, G. B.
System:
The UNT Digital Library
Engineering Test Reactor Critical Facility Control System Manual
This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date:
June 23, 1961
Creator:
Meichle, F. A.
System:
The UNT Digital Library
Engineering Test Reactor Critical Facility Hazards Summary Report, Supplement I
Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).
Date:
January 24, 1958
Creator:
deBoisblanc, D. R.; Burdick, Earl E. & DeBoer, T. K.
System:
The UNT Digital Library
Engineering Test Reactor : Engineering Design and Safeguards Report
From abstract: "Detail and engineering drawings for the Engineering Test Reactor."
Date:
July 1956
Creator:
Kaiser Engineers
System:
The UNT Digital Library
EOCR Control Rod and Driver Fuel Hydraulic Tests
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.
System:
The UNT Digital Library
ETR Nuclear Instrumentation : Final Report
Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date:
February 3, 1960
Creator:
Hanson, D. C.
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
Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation
From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
Date:
January 23, 1963
Creator:
Hartzfeld, H. A. & Regier, R. B.
System:
The UNT Digital Library
Experimental Organic Cooled Reactor : Conceptual Design
Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
Date:
December 1, 1959
Creator:
Huffman, John R.; Nyer, W. E. & Rainwater, J. H.
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
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, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office
Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date:
April 1, 1958
Creator:
ACF Industries Incorporated. Nuclear Products - ERCO Division.
System:
The UNT Digital Library
Final Summary Report of the Gas-Cooled Reactor Experiment-1
Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
Date:
October 1963
Creator:
Chesworth, R. H.
System:
The UNT Digital Library
Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)
Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).
Date:
September 1964
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation
Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
Date:
October 1963
Creator:
Phillips Petroleum Company
System:
The UNT Digital Library