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The Hydrolysis of Tributyl Phosphate Ad Its Effect on the Purex Process

Description: From abstract: "The rate of hydrolysis of TBP and the effect of the hydrolysis products in the Purex Process have been studied. Hydrolytic conditions may be encountered in the process which would lead to formation of dibutyl phosphoric acid, causing significant losses of tetravalent plutonium in stripping. This situation may be easily alleviated by reducing and stripping the plutonium in the trivalent state."
Date: December 13, 1951
Creator: Reilly, V. J. & Lanham, W. B.
Partner: UNT Libraries Government Documents Department
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Test of Heater and Cooler Concepts for OCR-ORR Loop, Design 4

Description: High heat flux electrical cartridge heaters were tested with direct air cooling under simulated ORR Loop conditions. The cartridges and the heater design were found to be satisfactory. A gas cooled of concentric pipe design utilizing air, water, and air-water mixtures as the coolant was also evaluated and found to be satisfactory.
Date: July 13, 1959
Creator: Kelley, W. H., Jr. & Storto, E.
Partner: UNT Libraries Government Documents Department
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Bibliography of ORNL-BSF Reports Pertinent to Swimming Pool Type Reactor Design (Revised)

Description: Much of the shielding work carried out with the Bulk Shielding Reactor (BSR) has yielded data of particular interest for the design of swimming pool type reactors, However, it is often difficult for a reactor designer to locate such data since it may be recorded in a report primarily concerned with shielding problems. Therefore, this memorandum presents a bibliography of reports from the Bulk Shielding Facility arranged according to the application of data to the various aspects of reactor desi… more
Date: April 13, 1956
Creator: Maienschein, F. C. & Johnson, E. B.
Partner: UNT Libraries Government Documents Department
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Chemistry Division Semiannual Progress Report for Period Ending December 20, 1955

Description: Semiannual Progress report of the Oak Ridge National Laboratory Chemistry Division providing updates on various projects, experiments, and other work in inorganic and physical chemistry, nuclear chemistry, organic chemistry, chemical physics, chemistry of separation processes, radiation chemistry, and reactor chemistry.
Date: April 13, 1956
Creator: Taylor, E. H. & Bredig, M. A.
Partner: UNT Libraries Government Documents Department
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Determination of Corrosion Products and Additives in Homogenous Reactor Fuel II. Polarographic Determination of Chromium

Description: A satisfactory ion-exchange-polarographic method was developed for the determination of either chromium(VI) or total chromium in Homogeneous Reactor fuels. Total chromium is determined as chromium (VI) , i.e., chromate, and in the same way as is chromium(VI), after chromium in the lower valence states is oxidized to chromate by potassium permanganate. Chromate is separated from all interfering metal ions in the fuel by ion exchange on a Dowex 50 resin column. The Chromate in the effluent is det… more
Date: September 13, 1955
Creator: Horton, A. D. & Thomason, P. F.
Partner: UNT Libraries Government Documents Department
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The Extraction and Recovery of Uranium (and Vanadium) from Acidic Liquors with DI (2-Ethylhexyl) Phosphoric Acid and Some Other Organophosphorus Acids

Description: Bench scale studies have been made of the recovery of uranium from acid leach liquors (and slurries) by solvent extracting with di (2-ethylhexyl) phosphoric acid in an organic diluent. Uranium may be stripped from the organic solvent by either alkaline or acidic reagents, the former having been studied in greater detail. On the basis of these tests, a recovery process may be considered which shows promise both from the standpoint of operation and chemical costs. Under proper conditions, vanadiu… more
Date: May 13, 1955
Creator: Blake, C. A.; Brown, K. B.; Coleman, C. F.; Horner, D. E. & Schmitt, J. M.
Partner: UNT Libraries Government Documents Department
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General Reactor-Engineering Research Quarterly Progress Report [for] Period Ending August 31, 1950

Description: Technical report describing results on work which cannot be ascribed to one reactor program. Outlines the results of miscellaneous corrosion testing, the development of new shielding materials, the testing of irradiated plastics, and general heat transfer investigation. [From Preface]
Date: November 13, 1950
Creator: Lyon, R. N.
Partner: UNT Libraries Government Documents Department
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Thermonuclear Project Semiannual Progress Report: for Period Ending July 31, 1960

Description: From Introduction: "The present semiannual progress report introduces more active consideration than has been given in the past (by us, at least) to the importance of energy degradation in DCX-like devices. The following pages introduce also a new major apparatus designated as DCX-2. Some of these concepts cannot as yet be released publicly and therefore Chap. 3 of this report, covering the DCX-EP-B design, is being issued separately, with restricted distribution, as ORNL-3044."
Date: January 13, 1961
Partner: UNT Libraries Government Documents Department
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Production Separations of Fission-Product Groups for the Radioisotope Program

Description: Report issued by the Oak Ridge National Laboratory discussing the production separation for the radioisotope program. As stated in the abstract, "a general description is given of five years' experience in routine production of fission products of high concentration and high activity levels for the radioisotope program. Details of construction and production processes are given for two systems which were built on ion-exchange principle" (p. 2). This report includes illustrations, and photograph… more
Date: August 13, 1952
Creator: Schallert, P. O.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1956

Description: This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and ether ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into three major parts: I. Reactor Theory, Component Development, and Construction, II. Materials Research, and III. Shielding Research.
Date: June 13, 1956
Creator: Jordan, W. H.; Cromer, S. J. & Miller, A. J.
Partner: UNT Libraries Government Documents Department
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Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed

Description: The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several poi… more
Date: August 13, 1964
Creator: Scott, Charles D.
Partner: UNT Libraries Government Documents Department
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Graduate Programs for the Health Physicist in the United States

Description: The first man-made nuclear reactor -- or "pile" as it was then called -- was rather hurriedly improvised and operated in a crowded space under the athletic bleachers of Stagg Field at the University of Chicago on December 2, 1942. Just prior to this time, there began the assembly of a group of physicists with an unusual assignment. They were determined that radiation hazards of unprecedented proportions must be coped with successfully in the conduct of reactor programs as planned. Since these p… more
Date: August 13, 1964
Creator: Morgan, K. Z. (Karl Ziegler), 1908-
Partner: UNT Libraries Government Documents Department
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Thermal Characteristics of Fluid Flow in Pipes

Description: An investigation is made to determine the adequacy of presently used analog circuits in solving dynamic fluid flow heat transfer equations. A mathematical analysis is made of dynamic heat transfer in pipes with zero losses, with losses proportional to pip temperature, and with heat inputs. The results of this analysis are compared with analog results by means of generalized temperature versus time graphs. The analog circuit is found to be adequate for most conditions, but sometimes requires mod… more
Date: September 13, 1960
Creator: Hinton, D. B.
Partner: UNT Libraries Government Documents Department
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Determination of Free Acid in Highly Radioactive Solutions by Remotely Controlled Conductometric Titration

Description: A conductometric titration method described by Goldstein was adapted for use in a remote analytical facility. The results obtained by mean of experiments made prior to this adaptation indicated that methanol is the most satisfactory medium in which to determine excess sulfuric acid in uranyl sulfate solutions that stimulate Homogeneous Reactor type fuel. When methanol is used, the complexation of hydrolyzable ions with sodium fluoride, as described by Pepkowitz, Sabol, and Dustin, is not requir… more
Date: October 13, 1960
Creator: Corcoran*, R. E.; Zittel, H. E.; Dinsmore, S. R. & Koskela, U.
Partner: UNT Libraries Government Documents Department
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EXPIRE - A Reactivity Lifetime Calculation

Description: EXPIRE is a calculation which predicts the reactivity-lifetime, instantaneous and integrated effective multiplication constants and instantaneous and integrated effective multiplication constants and instantaneous conversion ratio for heterogeneous reactors. The concentration of all the isotopes of interest from Th232 to Am243 are calculated as a function of time using the average reactor power density and a uniform flux distribution. The equations have been programmed for the IBM-704 computer … more
Date: October 13, 1960
Creator: Jaye, S.
Partner: UNT Libraries Government Documents Department
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Preparation of Thorium Oxide from ORNL Thorex Thorium Nitrate

Description: Thorium nitrate, recovered from irradiated thorium metal processed in the ORNL Thorex Pilot Plant, was converted to thorium oxide and then to the fluoride in one pilot-plant-scale and two laboratory-scale runs. Activity distributions, decontamination factors, and safety of the process are treated. (D.L.C.)
Date: February 13, 1957
Creator: McDuffee, W. T. & Yarbro, O. O.
Partner: UNT Libraries Government Documents Department
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Homogeneous Molten Salt Reactors

Description: Multigroup one-dimensional calculations were done recently to obtain estimates of critical masses, power density distributions and fissioning spectra for some homogeneous molten salt reactors having outer reflectors and central "islands," placed inside the currently proposed MSRE vessel. For a 5-inch-thick outer reflector and 1-ft-diamter island, both beryllium, the calculated critical mass is 108 kg; 40 percent of the fissions occur at thermal, and the maximum power density of 3.9 times the co… more
Date: December 13, 1960
Creator: Nestor, C. W., Jr
Partner: UNT Libraries Government Documents Department
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Processing of Beryllium Oxide Fuels

Description: Preliminary results from experiments on the dissolution of beryllium metal and sintered UO2-BeO fuel pellets are reported. In all cases the pellets were fired in hydrogen at 1650-1800°C. Uranium, from UO2-BeO pellets containing more than 60% UO2, is readily leached with boiling 6-13 M HNO3 in about 6 hr. The BeO in these pellets dissolves only slowly in nitric acid; however, in 8 M HNO3-0.2M NaF, it dissolves at about the same rate as the UO2. Sintered pellets containing less than 10% UO2 do no… more
Date: February 13, 1961
Creator: Warren, K. S. & Perris, L. M.
Partner: UNT Libraries Government Documents Department
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The Disposal of Power Reactor Waste Into Deep Wells

Description: For various reasons it is not possible to leave the uranium or other nuclear fuel in a power reactor until all of it has been "burned up" by fission. In the case of liquid fuel (homogeneous) reactors a small part is continuously bled out, purified and returned. In the case of solid fuel reactors, fuel elements are periodically removed, reprocessed and the "unburned" fuel put back into service. In both cases the purification produces wastes which contain radioactive fission products and transura… more
Date: June 13, 1957
Creator: De Laguna, Wallace, 1910- & Blomeke, J. O.
Partner: UNT Libraries Government Documents Department
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HRP In-Pile Corrosion Test Loops -- Operation of In-Pile Loop L-2-10

Description: Loop L-2-10 was the eighth completed in-pile loop experiment and the first in the HB-2 beam hole at the LITR. The loop was inserted on July 2, 1956 and removed on September 3, 1956. The installation, operation, removal, and general performance of the HRP in-pile solution corrosion loop in the HB-2 beam hole at the LITR are described.
Date: June 13, 1957
Creator: Walter, F. J.
Partner: UNT Libraries Government Documents Department
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Fuel Exposures in Heterogeneous Thorium Breeder Reactors

Description: This technical report summarizes some preliminary calculations of fuel exposures attainable in heterogeneous reactors, fueled with a mixture of thorium and U233, moderated with D2O and operated with no net loss in fissionable fuel.
Date: June 13, 1957
Creator: Prince, B. E. & Jaye, S.
Partner: UNT Libraries Government Documents Department
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Evaluation of Loop Components and Admixed Thorium-3% Uranium Oxide Slurry in 200A Loop (Summary of Run 200A-10)

Description: A slurry addition system, a venturi in the circulation loop, and two types of sampling systems were tested with 500 and 800 g Th/kg H2O slurries in the 200 gpm loop at 250 C and 1000 psig. The addition system worked satisfactorily while the venturi gave erratic readings during part of the run. Both the capillary and in-line sampling systems proved satisfactory with the capillary sampler being much easier and more convenient to operate. The addition of uranium to the slurry had no appreciable ef… more
Date: June 13, 1957
Creator: Gallaher, R. B.; Kitzes, A. S. & VandenBulck, C. F.
Partner: UNT Libraries Government Documents Department
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Apparent Observations Ionic Sound Waves in an Arc Plasma

Description: Oscillations have been observed in a magnetically supported cylindrical rod of plasma. This rod of plasma can be the discharge occurring in the defining aperture of a Mode II, pressure gradient arc. Similar oscillations can also occur in the column of a Mode I arc. These oscillations appear to be the mechanism that drives the Mode II blowup phenomena.
Date: February 13, 1961
Creator: Alexeff, I. & Neidigh, R. V.
Partner: UNT Libraries Government Documents Department
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Decontamination of EGCR Charge and Service Machines

Description: Methods for the noncorrosive removal of volatile fission products and UO2 dust from carbon steel and stainless steel have been developed. Procedures for applying these methods to the decontamination of the EGCR charge and service machines are described.
Date: October 13, 1960
Creator: Meservey, A. B.; Chilton, J. M. & Ferguson, D. E.
Partner: UNT Libraries Government Documents Department
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