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A Preliminary Survey of Radioactive Constituents in Rainwater at ORNL

Description: Technical report surveying radio-chemical analyses by ORNL's Analytical Chemistry Division and Health-Physics Division of large volumes of rainwater for plutonium, uranium, and fission products. Overall, carrying efficiencies for Al(OH)3 scavenging of rainwater were determined for these elements, as well as for Pu and U. [From Abstract, Introduction]
Date: December 4, 1950
Creator: Booksbank, W. A., Jr.; Emmons, A. H.; Gost, J. W. & Reynolds, S. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Oak Ridge National Laboratory Research Reactor Safeguard Report

Description: The proposed ORNL Research Reactor is designed to serve as a general purpose research tool delivering a maximum thermal flux of 8x10^13 n/cm2-sec at the initial power level of five megawatts. Operation at power levels up to ten megawatts is proposed for such items as sufficient cooling capacity is available to handle the increased heat load. The reactor will use MTR-type fuel elements and beryllium reflector pieces in a 7 x 9 grid with moderation and cooling provided by forced circulation of de… more
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Cost Analysis of the Idaho Chemical Processing Plant

Description: A capital cost breakdown of the Idaho Chemical Processing Plant, a directly maintained remotely operated plant for processing spent enriched uranium fuel assemblies from reactors, is presented. The capital investment in the plant, including design, construction, training, and preoperational costs, an estimate of the direct costs incurred by the Atomic Energy Commission, and a proportional part of the costs of Central Facilities, including the value of the land and improvements theorem when acqu… more
Date: January 4, 1955
Creator: Robertson, P. L. & Stockdale, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Oak Ridge National Laboratory Research Reactor Safeguard Report

Description: This memorandum sets forth a recommended uniform basis for designing the ORN shield.This includes design values for power level and emergent radiation, standards values for various material properties, and basic radiation intensities.
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electronuclear Research Division Semiannual Progress Report

Description: Nuclear physics research with 22-Mev protons in the 86-in. cyclotron included angular-distribution measurements of neutrons from (p,n) reactions in nine target elements; measurement of the angular distribution of fission fragments from proton-induced fission of U233, U225, U228, Th230, and Th232; measurement of alpha-particle angular distributions from (p,α) reactions a study of the neutron-deficient isotopes of terbium and completion of an extensive program of the measurement of activation cr… more
Date: November 18, 1954
Creator: Livingston, R. S. & Howard, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Acidity and Reducing Agents on Ruthenium Solvent Extraction by Tributyl Phosphate in the 25 Process

Description: Results of tracer studies suggest that, in tributyl phosphate extraction processes designed to recover and purify fissionable material, minimum ruthenium extraction should be obtained from feeds at least 2 M in nitric acid or at least 1 M acid-deficient. Ruthenium decontamination was decreased by preheating the feed and increased by pretreatment with reducing agents. A pretreatment using 0.06 M ferrous ion and 0.5 M urea with 1 hr simmering at 85°C should increase ruthenium decontamination abou… more
Date: December 15, 1954
Creator: Flanary, J. R. & Frashier, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Combination of Hydrogen and Oxygen in Platinum Catalyzed Flow Reactions

Description: An extension of the concepts advanced by Langmuir regarding the nature of the platinum catalyzed oxidation of hydrogen and the application of the resulting theory to the experimental data observed by Ranschoff and Spiewak for an HRE type recombiner indicates that their data are corrected by the dimensionless equation (see report) equally well, with a mean deviation of 3.8 percent. This expression is recommended as a basis for the design of catalytic recombiners. The catalytic combinations is pi… more
Date: October 26, 1954
Creator: Garber, Harold J. & Peebles, Fred N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: For Period Ending October 31, 1954

Description: Part I. Experimental Reactors: The design has been completed for all the major high-pressure and low-pressure components except the reactor pressure vessel. Contained in this report are the most recent revisions of the low-pressure-system flow sheet, a description of important details of the reactor cell, and the final design of the main heat exchangers, the inner dump tanks and separator. the recombiner and recombiner-condenser, and the outer dump tank and reflux condenser. Part II. Thorium Br… more
Date: November 1954
Creator: McDuffie, H. F. & Kelly, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Products Produced in Continuous Neuron Irradiation of Thorium

Description: Calculated data and graphs describing the effects of continuous thermal-neutron irradiation of thorium, the usual method of operations of homogeneous reactors, are presented.The buildup and decay of U^233, Pa^233, other heavy isotopes, and fission products are considered on the basis of best available cross-section and fission-yield data. The effects of the heavy isotopes and fission products on neutron economy are discussed.
Date: February 16, 1956
Creator: Gresky, A. T. & Arnold, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Products Produced in Batch Neutron Irradiation of Thorium

Description: Calculated data and graphs describing the effects of batch thermal-neutron irradiation of thorium, the usual method of operation of heterogeneous reactors, are presented. The buildup and decay of U233, Pa233, other heavy isotopes, and fission products are considered on the basis of best available cross-section and fission-yield data. The effects of these irradiation products on the Thorex chemical separation process are indicated briefly.
Date: December 27, 1955
Creator: Gresky, A. T. & Arnold, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stable Isotope Research and Production Division Semiannual Progress Report

Description: The Spectroscopy Research Laboratory is concerned with research and development in the fields of nuclear magnetic resonance, microwaves, infrared and optical spectroscopy, spectrochemistry, and x rays. Research is directed toward fruitful methods of isotope analysis; new element and compound analytical methods having application to immediate Laboratory or long-range commission needs; and fundamental research on isotopes, elements, and compounds. The work is reported on a project basis to give a… more
Date: February 18, 1955
Creator: Keim, C. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Test Summary Report for the Advisory Committee on Reactor Safeguards

Description: The Homogeneous Reactor Test (HRT) is the experimental reactor facility (Frontispiece) being designed and constructed at ORNL as the next step in homogeneous reactor development between the 1-Mv HRE and a "full-scale" power station. The HRT will provide an integrated test at 5 to 10 Mv for the flowsheet and equipment designs on which the full-scale effort will be based. Furthermore, its design is such that several homogeneous systems which require essentially the same operating equipment may be… more
Date: January 5, 1955
Creator: Beall, S. E. & Visner, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aircraft Reactor Test Hazards Summary Report

Description: The successful completion of a program of experiments, including the Aircraft Reactor Experiment (ARE), has demonstrated the high probability of producing militarily useful aircraft nuclear power plants employing reflector-moderated circulating-fuel reactors. Consequently, and accelerated program culminating in operation of the Aircraft Reactor Test (ART) is under way. In order to adhere to the compressed schedule of the accelerated program, it is essential that the Atomic Energy Commission app… more
Date: January 19, 1955
Creator: Cottrell, W. B.; Ergen, W. K.; Fraas, A. P.; McQuilkin, F. R. & Meem, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Monte Carlo Estimation of the High Energy Neutron Flux Distribution in the ORNL Graphite Reactor

Description: The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estima… more
Date: February 23, 1955
Creator: Moshman, Jack
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mathematics Panel Semiannual Progress Report

Description: From July through December, a total of 1750 hr of computer time was used by programmers in "debugging" and in running problems. With the acquisition of a second operator, the evening shift was initiated. A night-shift operator is presently being trained, and third-shifts operations will probably begin after completion of the magnetic-tape memory. / Engineering time is regularly scheduled for 4 hr each morning and 1/2 hr late in the afternoon. An electronic technician is on duty during evening-s… more
Date: March 2, 1955
Creator: Householder, A. S. & Sangren, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report For Period Ending February 28, 1955

Description: This semiannual progress report and future reports will be published as two documents to permit a wider distribution of the unclassified material. The report numbers are assigned in sequence so that the two reports will fall together when filed by report number.
Date: July 12, 1960
Creator: Billington, D. S. & Crawford, J. H., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogenous Reactor Project Quarterly Progress Report For Period Ending January 31, 1955

Description: The reactor equipment cell is expected to be completed by February 15. While filled with water, the tank was inspected for leaks, and the few leaks found will have been repaired by February 15. All orders for construction materials placed prior to this quarter have been received. New requisitions issued during the quarter total $16,000. Work orders were issued, and fabrication of all low-pressure-system components was begun in the ORNL shops. The thermal shield around the reactor vessel was spe… more
Date: April 6, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Plutonium and Uranium in Scrup Dissolver Solutions

Description: Methods for the determination of plutonium and uranium in highly radioactive scrup dissolver solutions have been developed. Plutonium was separated from the dissolver solutions by solvent-extraction and ion-exchange techniques and determined by potentiometric titration. Uranium was separated by ion exchange and determined by potentiometric titration. Solutions that were similar to the actual dissolver solutions and that contained known amounts of plutonium and uranium were analyzed by these met… more
Date: July 14, 1955
Creator: Foster, R. W.; Cooper, J. H. & Raaen, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Isolation and Purification of Americium

Description: Gram amounts of americium were separated quantitatively from kilogram quantities of lanthanum to yield an americium product approaching 90% purity. The remaining impurity was chiefly yttrium. Elution of americium from 25% loaded Dowex 50 resin column with 0.15 M citric acid— 0.10 M diammonium citrate — 0.3 M ammonium nitrate, pH 3.3 gave a product containing 99% of the americium with a La/Am ratio of 1/100 or less in one fourth of a column volume, in this case about 1 100-fold volume reduction.… more
Date: April 17, 1956
Creator: Campbell, D. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Disassembly and Postoperative Examination of the Aircraft Reactor Experiment

Description: The Aircraft Reactor Experiment (ARE)was successfully concluded in November of 1954, and a detailed report of the operation was published the following year. At that time it was thought that an extensive examination of the reactor and system components after disassembly was warranted. It was realized, of course, that the level of radioactivity of the components would necessitate extensive delays in the examinations. Since examination of a few critical ARE samples showed nothing unexpected, much… more
Date: April 15, 1958
Creator: Cottrell, W. B.; Crabtree, T. E.; Davis, A. L. & Piper, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Monex Process: Terminal Report

Description: Chemical and engineering data were obtained for the feed digestion system and the extraction-scrub step of the Monex tributyl phosphate solvent-extraction process for recovering thorium and uranium from nitric acid-digested unclarified monasite sludge. Tests of the recommended conditions in a 2-in.-dia pulsed column demonstrated that thorium losses were approximately 1.2% and uranium losses, 1.5%. The flowsheet is workable but is not necessarily optimum.
Date: January 31, 1958
Creator: McNamee, R. J. & Wischow, R. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Separation of Isotopes Section Semiannual Progress Report For Period Ending December 31, 1954

Description: New systems involving the exchange of boron between boron trifluoride and boron trifluoride addition compounds have been explored. These systems have large separation factors and potentially simple reflux mechanisms. A precise determination of this separation factor for the anisole-boron trifluoride system gave the value (see report). Boron exchange was found to occur between BF and BCl3. Several homogenous catalysts have been found which activate the hydrogen-water exchange, but none are adopt… more
Date: May 20, 1955
Creator: Clewett, G. H & Drury, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dissolution of Metals in Fused Fluorides

Description: In scouting tests, a number of metals used in nuclear reactor fuel elements were dissolved by 44.5-48.5-7.0 mole % ZrF4-KF-NaF fused salt at 675°C through which HF was being passed. These included type 304 stainless steel at 4 mils/hr; type 347Nb stainless steel at 7 mils/hr; thorium at 14 mils/hr; nonirradiated uranium at 17 mils/hr; zirconium at 22-35 mils/hr; titanium at 31 mils/hr; and Zircaloy-2 at 22-46 mils/hr. Only small amounts of volatile fission products formed when irradiated uraniu… more
Date: October 12, 1953
Creator: Leuze, R. E.; Cathers, G. I. & Schilling, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry Division Semiannual Progress Report For Period Ending April 20,1955

Description: The development of ionic methods for the determination of corrosion products in the highly radioactive Homogeneous Reactor (HR) fuels has been of major interest in the work of the Ionic Analyses Laboratory. Methods for the spectrophotometric determination of aluminum and for the polarographic determination of iron in HR fuels have been developed. The polarographic determination of molybdenum in uranyl sulfate solutions was studied. A polarographic method for the determination of zinc was develo… more
Date: May 6, 1955
Creator: Kelley, M. T.; Susano, C. D. & Raaen, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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