Office of Scientific & Technical Information Technical Reports - 189 Matching Results

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THE ABSOLUTE ABUNDANCE OF THE CHROMIUM ISOTOPES IN SOME SECONDARY MINERALS

Description: Isotopic assays have been made on the Cr in samples from 14 different chrominiferous minerals from different geographic and meteoritic sources. The results of the assays indicate that it is not possible to state unequivocally that variations in isotopic composition have been observed. (auth)
Date: March 14, 1962
Creator: Svec, H. J.; Flesch, G. D. & Capellen, J.
Partner: UNT Libraries Government Documents Department
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Activity of irradiated regular metal in buckets

Description: The potential of shipping a bucket of metal that has not had sufficient decay time is a common problem to all Reactor Processing Operations. The only method at present to assure shipping adequately decayed metal is by procedural control. This study was performed to determine the feasibility of establishing decay time for irradiated metal in buckets by radiation activity measurements.
Date: September 14, 1964
Creator: Smith, R. H.
Partner: UNT Libraries Government Documents Department
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Analog program in reactor speed of control studies

Description: One of the characteristics of the safety control system of the Hanford reactors which is of primary concern from the standpoint of reactor safety is the response time. The purpose of this study is to determine whether the safety control system is sufficiently fast-acting to prevent an intolerably large power excursion from developing. An intolerably large power excursion is one that would cause a melting of the uranium while the reactor power is above the previous operating level. The purpose o… more
Date: June 14, 1961
Creator: Cameron, W. D. & Tiller, R. E.
Partner: UNT Libraries Government Documents Department
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ANALYSIS--GRAPHITE CORE STRUCTURE

Description: A study was made to determine the structural and functional adequacy of the EGCR graphite core design. Maximum stress and distortion of the core and the probable operating time before graphite cracking were determined. The major cause of stress is non-uniform fast-neutron flux, which causes non-uniform shrinkage of graphite components. The critical stress was found to be tensile. The criterion for determining the time of cracking of graphite columns appears to be the point at which the creep st… more
Date: December 14, 1960
Creator: Newton, R.R.
Partner: UNT Libraries Government Documents Department
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Analysis Of Activation Measurements Of Th$sup 232$ Resonance Captures In The Peach Bottom (40-MW(E) Prototype HTGR) Critical Assembly

Description: Measurements of thorium resonance-capture activations relative to those of Au/sup 197/, which were made in the Peach Bottom (HTGR) critical assembly, are analyzed and compared with thorium resonance activations calculated from tabulated values of the resonance parameters. The new vanadium-subtraction method that was applied is shown to measure thorium resonance captures relative to those of Au/sup 197/ to within several per cent in this geometry. The measurements show that the lowest several re… more
Date: September 14, 1962
Creator: Sampson, J. B.
Partner: UNT Libraries Government Documents Department
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Aqueous Processes for Dissolution of Uranium-Molybdenum Alloy Reactor Fuel Elements

Description: Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric acid--ferric nitrate, and nitric acid-- phosphoric acid solutions were studied on a laboratory scale. Flowsheets based on the results propose dissolution of alloys containing 3% molybdenum in boiling 6 M HNO/ sub 3/ to yield stsble solutions that are 0.6 M in uranium and 3 to 4 M in nitric acid. The uranium can then be easily decontaminated and recovered in a conventional Purex-type tributyl phosph… more
Date: July 14, 1961
Creator: Ferris, L. M.
Partner: UNT Libraries Government Documents Department
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Aqueous Processing of Thorium Fuels

Description: The status of aqueous processing methods for thorium fuels is summarized, with principal emphasis on the stainless steel-clad ThO/sub 2/UO/sub 2/ type. Data were obtained principally from laboratory-scale experiments with fully irradiated fuel samples and engineering-scale tests with unirradiated fuel. Stainless steel cladding was easily dissolved with 4 to 6M H/sub 2/SO/sub 4/ (Sulfex process) or 5M HNO/sub 3/-2M HCl (Darex process) in LCNA (Nionel type) or titanium equipment, respectively, in… more
Date: March 14, 1962
Creator: Blanco, R. E.; Ferris, L. M. & Ferguson, D. E.
Partner: UNT Libraries Government Documents Department
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Army Reactors Program Progress Report

Description: Research and development on metallurglcal aspects of pressurized-water systems is summarized. A survey was made of the methods of determining fuel burnup. The mechanisms and kinetics of the loss of boron during heating at 1135 deg C in various dynamic environments were determined. A model was developed to quantitatively characterize the UO/sup 2/ dispersion microstructure of roll-clad fuel plates relative to an ideal'' dispersion. In order to avoid the loss of boron from UO//sub 2/- stainless s… more
Date: February 14, 1962
Partner: UNT Libraries Government Documents Department
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Basic Studies of Chemical Stability in Extraction Systems. I. The Effect of Zirconium Nitrate and Nitric Acid Upon the Chemical Stability of Tributyl Phosphate

Description: The effect of extracted zirconium and nitric acid upon the chemical stability of tributyl phosphate was investigated using gas-liquid chromatography. Tributyl phosphate was degraded approximately 1000 times faster by the tributyl phosphate-zirconium reaction than by the tributyl phosphatenitric acid reaction. Normal butyl nitrate was the major volatile product for both systems studied; with extracted zirconium a solid complex corresponding to the formula Zr(NO/sub 3/ )/sub 2/(DBP)/sub 2/ was al… more
Date: April 14, 1961
Creator: Moffat, A. J. & Thompson, R. D.
Partner: UNT Libraries Government Documents Department
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Coincident Trip Pressure Monitors

Description: At your request the Plant pressure monitor scram history for the period covering January 1, 1960, through June 31, 1963, was reviewed to predict the production saving that would result if a reliable pressure monitor dual-trip feature were added to the six old reactors.
Date: November 14, 1963
Creator: Newell, L. J. & Spencer, H. G.
Partner: UNT Libraries Government Documents Department
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Comment issue - Production Test IP-333-D: Irradiation of one defected UO{sub 2} fuel element assembly

Description: To permit the irradiation of one dummy fuel element assembly for one operating period and to permit, during a subsequent operating period, the irradiation of one defected, four-rod-cluster UO{sub 2} fuel element assembly, in a KE front-to-rear test hole. The fuel material is natural UO{sub 2} of 95 per cent theoretical density; the cladding is zircaloy. The defect in the assembly is artificial and will be made before irradiation by drilling a .005in. diameter hole through the cladding near the … more
Date: June 14, 1960
Creator: Marshall, R. K.
Partner: UNT Libraries Government Documents Department
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Compact Thermoelectric Converter. Phase II-A. Quarterly Progress Report, January 1-March 31, 1966

Description: The objectives for Phase II, Module Development, are to perform detailed module deign and analyses; to develop and evaluate module components, and fabrication and assembly processes; and to conduct development testing on module components and complete modules in order to evaluate performance, environment capability, failure modes, quality control and long-term behavior.
Date: April 14, 1966
Partner: UNT Libraries Government Documents Department
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Compact Thermoelectric Converter. Phase Ii-A. Quarterly Progress Report, July 1-September 30, 1966

Description: The ultimate objectives of the Compact Thermoelectric Converter Program are to develop and qualify for space applications a reliable, high performance thermoelectric module and, if required, other converter hardware for use in 1 to 20 kilowatt (electric) compact thermoelectric converters.
Date: October 14, 1966
Partner: UNT Libraries Government Documents Department
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Composition of ending inventory, May 1966

Description: Submitted herewith are source and special nuclear material composition of ending reports for the month of May 1966. Production processes and products and weapons process and products are accounted along with nonproduction reactors R&D.
Date: June 14, 1966
Creator: Budd, R. O.
Partner: UNT Libraries Government Documents Department
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Composition of ending inventory, November 1966

Description: Submitted herewith are source and special nuclear material composition of ending inventory reports for the month of November 1966. The depleted uranium, enriched uranium, plutonium, enriched lithium, U-233, normal uranium, neptunium 237, plutonium 238, deuterium, tritium, and thorium compositions are all broken down.
Date: December 14, 1966
Creator: Budd, R. O.
Partner: UNT Libraries Government Documents Department
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