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In-Pile Slurry Loop Program

Description: The in-plie slurry loop work is now being considered as a joint program between the PAR project and ORNL. It is proposed that PAR design, fabricate and test the in-pile loops and that ORNL operate the loops in-pile, dismantle the loops after irradiation and made the appropriate measurements to determine the radiation effects. This report gives the objects of the slurry in-pile program and outlines the facilities and operations required to execute ORNL's part of this program.
Date: March 8, 1957
Creator: Arehart, T. A.; Compere, E. L. (Edgar L.); Ferguson, D. E.; Korsmeyer, R. B. & McBride, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analog Study of the Reference Design of the Gas-Cooled ORR Loop No. 1

Description: A stimulation study of the deign as of June 1960 of the gas-cooled ORR Loop No. 1 was made using the ORNL analog computer. The proposed method of temperature control is evaluated, and the dynamic behavior of the loop for accidents and component failures is presented in graphical form.
Date: November 8, 1960
Creator: Ball, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Rate of Uranium Sorption by a Strong-Base Anion-Exchange Resin

Description: The rate of uranium sorption by a strong-base anion-exchange resin (Dovex 21K) from a uranyl sulfate solution (U 0.005 M, H2SO4 0.02M, SO4 0.2 M) was studied using a stirred vessel technique and measuring the U235 gamma radiation on each bead. Resin initially in the chloride form and the sulfate for was studied.
Date: July 8, 1959
Creator: Bresee, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Monthly Progress Report August 1959

Description: Uranium extractions from carbonate solutions were effective and phase separation rates were rapid using a new commercial quaternary extractant, Alamine 336. Extraction coefficients were approximately proportional to the quaternary concentration. Addition of -0.5 mole tridecanol/mole quaternary to the solvent gave optimum extraction efficiency and phase separation rates.
Date: September 8, 1959
Creator: Brown, K. B.; Allen, K. A.; Coleman, C. F.; Crouse, D. J. & Ryon, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Maintenance of Various Reactor Types

Description: This technical report presents an overview of nuclear reactor maintenance to be used in planning a nuclear reactor. There are certain basic maintenance fundamentals that are common to all types of reactors that may be' incorporated in a power producing facility. Basically, there are only two types of maintenance procedures. The direct type, which is common to conventional steam plants, may be used in some areas where the radioactivity is low enough. In most parts of the plant, maintenance will … more
Date: April 8, 1957
Creator: Draper, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of HRT Run 14

Description: This report presents a detailed study of HRT Run 14, which was abruptly terminated by the formation of a hole in the Zircaloy-2 core tank. In this run the reactor was operated at high temperature and pressure for ten days from March 25 to April 4, 1958. Nuclear power operation extended from March 29 until April 4, when fuel solution leaked into the heavy-water blanket. The maximum power level attained was 6.4 Mw.
Date: June 8, 1959
Creator: Engel, J. R.; Haubenreich, P. N.; Kolb, J. O. & Richardson, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Design of a 10-Mw(t) Pebble-Bed Reactor Experiment

Description: The objectives of this study have been to examine the problems of the pebble-bed reactor concept and to conceive a design of a facility for investigating the feasibility of this type of reactor. The design must provide for adequate leaktightness of the contaminated-gas system and adequate maintenance of contaminated components, the most vital feasibility questions of the concept.
Date: May 8, 1961
Creator: Fraas, A. P.; Carlsmith, R. S. & Corum, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950

Description: Technical report outlining the rate of production of modified MTR type fuel elements for the Bulk Shielding Facility has proceeded. Includes compatibility test that were started as a guide in the selection of materials suitable for fuel-element fabrication. [From Summary]
Date: February 8, 1951
Creator: Frye, J. H.; Miller, E. C. & Bridges, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HRT Source Shield Calculations

Description: Calculations indicate that the proposed shielding arrangement will give a dose rate at the surface of the water tank of about 100 mrem per hr., practically all gammas. This is adequate for transportation and handling, but if the radiation actually proves to be this high, a storage location isolated from normal working areas must be provided. The isolation area need not be large, however, since the calculated dose rate at 10 feet from the shielded sources is only 3.5 mrem pr hr. For the short ti… more
Date: January 8, 1957
Creator: Haubenreich, P. N. & Rivenbark, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Technology Division Pilot Plant Section Report for November, 1950- January, 1951

Description: Technical report presenting a summary of the flowsheets, equipment, and progress for the Oak Ridge National Laboratory (ORNL) pilot plant development of the Purex Process and of the ORNL Metal Recovery Program. As of this report, conversion of the Purex pilot plant equipment in Buildings 3019 and 3503 is 90% complete. The building structure for the ORNL Waste Metal Recovery plant had been completed, and 15% of the process equipment had been installed. The first hot runs for this plant were sche… more
Date: March 8, 1951
Creator: Jackson, H. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Costs in Batch- and Continually-Processed Homogeneous Reactors

Description: The fuel requirement of a heavy-water moderated, homogenous, power reactor were estimated for a variety of initial loadings, for both bath and continuous methods of fuel removal. This study considered a 12-ft spherical reactor, temperature 250 C, 500 Mw thermal power, 125 Mw electrical power capability, 0.8 load factor, and 4%/year inventory charges for U and D2O. The fuel shipping-and-processing charges were assumed to be $1/gm of fissionable fuel for the "batch" processed reactors, and $0.37/… more
Date: February 8, 1957
Creator: Kasten, Paul R. & Aven, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analytical Chemistry Division Quarterly Progress Report for Period Ending March 26, 1951

Description: Technical report covering experiments happening on the Analytical Chemistry Division's sites at the Oak Ridge National Laboratory. Includes information on ionic analyses, radio-chemical analyses, spectrochemical analyses, service analyses, inorganic preparations, analytical chemical control of homogeneous reactor solution, optical and electron microscopy, and service analyses for the period ending March 26, 1951. [From Abstract]
Date: October 8, 1951
Creator: Kelley, M. T. & Susano, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Attenuation in Water of Radiation from the Bulk Shielding Reactor: Measurements of the Gamma-Ray Dose Rate, Fast Neutron Dose Rate, and Thermal-Neutron Flux

Description: Report issued by the Oak Ridge National Laboratory displaying a single chart showing measurements of the gamma-ray, fast-neutron, and thermal-neutron dose rates.
Date: July 8, 1958
Creator: Oak Ridge National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fission Product Release from UO2 and by High Temperature Diffusion and Melting in Helium and Air.

Description: The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release… more
Date: February 8, 1961
Creator: Parker, G. W.; Creek, G. E. & Martin, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Extraction of Metal Ions with Di-2-Ethylhexyl Phosphoric Acid

Description: Blake and his co-workers have shown that uranium and other elements can be extracted from acid solutions by various type of organo-phosphorous compounds. Early investigations in the laboratory have demonstrated the applicability of tri-n-alkyl phosphine oxides to the extraction of metal ions from acidic solutions for analytical purposes. This paper is concerned with a similar qualitative investigation of the extraction of metal ions with a di-alkyl phosphoric acid, di-2-ethylhexyl phosphoric ac… more
Date: February 8, 1957
Creator: Ross, W. J. & White, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calculations for Irradiation of Natural UO2-ThO2

Description: Calculations are given for eighteen stainless steel clad helium bonded specimens of UO2-ThO2 containing normal U to be placed in 6 holes in a holder in a position of the ORR not to exceed a peak unperturbed flux of 4 x 10^14 n.cm^2/sec and irradiated to a peak nvt of 1.96 x 10^21 neutrons/cm^2
Date: June 8, 1959
Creator: Ullmann, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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