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Status Report Number Three on Clinch River Study

Description: Report describing the progress made in the Clinch River Study for the period May to October 1961. This report is based off of multiple reports of water sampling conducted across six stations in order to evaluate the safety and radioactive content of the Clinch River.
Date: December 6, 1962
Creator: Morton, R. J.
Item Type: Refine your search to only Report
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Nuclear Merchant Ship Reactor Final Safeguards Report, Volume 6: Environmental Analysis OF NS "Savannah" Operation at Camden

Description: "An analysis is presented of the accidental release of activity following the operation of the NS "Savannah" at the New York Shipbuilding Corporation docks in Camden, New Jersey. Although a number of accidents are considered, the report is primarily concerned with the environmental activity levels and subsequent exposures which would result from the "maximum credible accident" (p. v).
Date: January 24, 1961
Creator: Cottrell, W. B.; Parker, F. L.; Mann, L. A. & Schmidt, G. D.
Item Type: Refine your search to only Report

[3D Viewer]

Description: Black cardboard viewer with plastic lenses, "for printed stereo photographs." It has scored portions and instructions for folding the cardboard to create a standing viewer to look through the lenses and keep the image at a distance.
Date: 1965
Creator: Stereo Magniscope, Inc.
Item Type: Refine your search to only Physical Object
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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
open access

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 deā€¦ more
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J. P.
Item Type: Refine your search to only Report
open access

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 acquā€¦ more
Date: January 4, 1955
Creator: Robertson, P. L. & Stockdale, W. G.
Item Type: Refine your search to only Report
open access

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,Ī±) reactions a study of the neutron-deficient isotopes of terbium and completion of an extensive program of the measurement of activation crā€¦ more
Date: November 18, 1954
Creator: Livingston, R. S. & Howard, F. T.
Item Type: Refine your search to only Report
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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 85Ā°C should increase ruthenium decontamination abouā€¦ more
Date: December 15, 1954
Creator: Flanary, J. R. & Frashier, L. D.
Item Type: Refine your search to only Report
open access

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 piā€¦ more
Date: October 26, 1954
Creator: Garber, Harold J. & Peebles, Fred N.
Item Type: Refine your search to only Report
open access

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 Brā€¦ more
Date: November 1954
Creator: McDuffie, H. F. & Kelly, D. C.
Item Type: Refine your search to only Report
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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
open access

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
open access

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 aā€¦ more
Date: February 18, 1955
Creator: Keim, C. P.
Item Type: Refine your search to only Report
open access

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 beā€¦ more
Date: January 5, 1955
Creator: Beall, S. E. & Visner, S.
Item Type: Refine your search to only Report
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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 appā€¦ 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
open access

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 estimaā€¦ more
Date: February 23, 1955
Creator: Moshman, Jack
Item Type: Refine your search to only Report
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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-sā€¦ more
Date: March 2, 1955
Creator: Householder, A. S. & Sangren, W. C.
Item Type: Refine your search to only Report
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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 speā€¦ more
Date: April 6, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
Item Type: Refine your search to only Report
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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 metā€¦ more
Date: July 14, 1955
Creator: Foster, R. W.; Cooper, J. H. & Raaen, H. P.
Item Type: Refine your search to only Report
open access

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 acidā€” 0.10 M diammonium citrate ā€” 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.ā€¦ more
Date: April 17, 1956
Creator: Campbell, D. O.
Item Type: Refine your search to only Report
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