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MTR Technical Branch Quarterly Report for First Quarter - 1954

Description: The following report is a quarterly report for first quarter in 1954 for the Phillips Petroleum Company. During the first quarter of 1954 considerable progress was made on the design, construction and testing required to initiate work on new programs. The result of this is the beginning construction and design on the Reactivity Measurement Facility.
Date: December 5, 1955
Creator: Huffman, J. R.
Partner: UNT Libraries Government Documents Department
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Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)

Description: The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: April 1, 1962
Creator: Rider, B. F.
Partner: UNT Libraries Government Documents Department
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The Materials Testing Reactor

Description: The following report describes a reactor that was designed to provide a research facility for testing various materials in a high intensity radiation field.
Date: September 24, 1953
Creator: Weber, L. J.
Partner: UNT Libraries Government Documents Department
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Operating Manual for the MTR, Section Two -- Exclusion Area, Materials Testing Reactor

Description: From summary: "This manual is designed for the purpose of clarifying operating procedures of the Materials Testing Reactor and its associated equipment. In assembling this manual a description of each item of equipment and its function is presented. In addition, the generally accepted method of operating the equipment and the best corrective measures concerning all emergencies that might be encountered are set forth herein. Descriptive drawings and written instructions pertaining to the equipment have been included to further clarify the manual."
Date: 1955
Creator: Phillips Petroleum Company. Atomic Energy Division.
Partner: UNT Libraries Government Documents Department
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Production of Xe¹³¹, Xe¹³⁵, Kr⁸⁵m and Kr⁸⁵ From Plated-Out U²³⁵ in the MTR Core

Description: This report discusses details of the release of Xe¹³¹, Xe¹³⁵, Kr⁸⁵m and Kr⁸⁵ into the process water system of the MTR along with the development of high process water radioactivity. It is suggested that this release followed the fissioning of U²³⁵. Equations that produce the rate of release of fission products is given and approximate rate of release is represented in a graph.
Date: January 14, 1955
Creator: Grimaud, Adrian V.
Partner: UNT Libraries Government Documents Department
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The Quantitative Techniques of Scintillation Spectrometry as Applied to the Calibration of Standard Sources

Description: Report presenting "the determination of absolute gamma emission rates for monoenergetic gamma emitters using a single-channel scintillation spectrometer. Examples are given for Cr⁵¹, Cs¹³⁷, Nb⁹⁵, and Zn⁶⁵. Sources of error are discussed and steps being taken to improve the accuracy of the method are described" (p. 1).
Date: April 25, 1955
Creator: Heath, R. L. & Schroeder, F.
Partner: UNT Libraries Government Documents Department
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Proposal for an Advanced Engineering Test Reactor : ETR II

Description: Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
Date: March 17, 1960
Creator: deBoisblanc, D. R.
Partner: UNT Libraries Government Documents Department
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Flux Distributions and Critical k [infinity] Values for Cylindrical Reactors Simulation the MTR

Description: From summary: "In order to estimate the effect of placing bismuth and thorium layers near the MTR core, radial flux distributions and k[infinity] values were calculated for cylindrical reactors having cylindrical layers of these materials of the same height as the core and beryllium reflector and placed either next to the core or embedded in the beryllium reflector."
Date: June 25, 1952
Creator: Bray, D. T. & McMurry, Henry Lewis, {}
Partner: UNT Libraries Government Documents Department
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Corrosion of Aluminum and Beryllium by MTR Canal Water

Description: Introduction: "In the early operation of the WTR severe canal corrosion of dummy fuel assemblies and a beryllium A-piece caused a great deal of concern as to the possible effects of long-time canal storage on such elements. A short-term experimental program was started to determine the causes of this corrosion and to correct them before any irradiated fuel elements had to be stored in the canal. The results of this program are presented here."
Date: January 14, 1953
Creator: Burnham, J. B., Jr. & Bartz, M. H.
Partner: UNT Libraries Government Documents Department
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Evaluation of Sampling Variables : Vessel C-102

Description: Purpose: "In order to determine the optimum procedure for sampling the coarse-feed tank (C-102) of the NP and MTR process, a systematic series of tests has been conducted to measure the extent of solution stratification and effect of air-sparging as a means of vessel homogenization."
Date: September 3, 1954
Creator: Loopstra, H. B.; Tingey, Fred H. & Vance, F. P.
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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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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