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5-gpm In-Pile Thorium Oxide Slurry Loop Development, Runs 14 Through 16 In Loop L-4-248, And Filtration Of Thorium Oxide Slurry With Sintered Filters

Description: In in-pile pump loop capable of circulating thorium oxide slurry while exposed to nuclear radiation in an experimental reactor beam hole is necessary to obtain information on the effect of reactor radiation on the physical and chemical properties of the slurry and on the corrosion-erosion of containment materials. Thorium oxide filtration test results with various sintered-metal filters and one aluminum oxide filter are reported.
Date: March 7, 1960
Creator: Baker, J. M.; Jones, D. T. & Savage, H. C.
Item Type: Refine your search to only Report
open access

An 80 Megawatt Aqueous Homogeneous Burner Reactor. Reactor Design and Feasibility Problem

Description: An 80 Mw aqueous homogeneous burner reactor suitable for producing 20 Mw of electricity at a remote location is described. The reactor fuel consists of a light water uranyl sulfate solution which acts as its own moderator and coolant. The uranium is highly enriched (93% U/sup 235/). The primary considerations for the design were simplicity and reliability of the components, automatic demand control and safe for any load change, full xenon override not required, possibility of construction withi… more
Date: August 1957
Creator: Chapman, R. H.; Collins, H. L.; Dollard, W. J.; Fieno, D.; Hernandez-Fragoso, J.; Miller, J. W. et al.
Item Type: Refine your search to only Report
open access

200 MW Nuclear Power Station Using a Natural Uranium, Organic Cooled, Heavy Water Moderated, Heterogeneous Power Reactor : Reactor Design and Feasibility Study

Description: A preliminary design and feasibility study is presented for an organic cooled, heavy water moderated, natural uranium fuel, heterogeneous reactor for a central station power plant with an electrical capability of 200 Mw. This study indicates that such a plant is capable of producing electrical energy in the range of 0 to 7 mills/kwh with burnups of the order of 3000 Mwd/ ton. The use of organic coolants permits high temperature operation at low pressure and thereby eliminates the necessity for … more
Date: August 1957
Creator: Veras, A. F.; Beal, F. S.; Hartfield, G. L.; Irwin, H. D.; Licitra, E. A.; Lill, H. I., Jr. et al.
Item Type: Refine your search to only Report
open access

2G-2R Spherical Reactor Code For The IBM-704

Description: A code has been written for the IBM-704 computer that is essentially the same as the 2G-2R ORACLE code with some added features which make the present code more general. Both the core and blanket can handle two fuel components, moderator, fertile material (Th-232 or U-238), poison, and 5 additional components. Provisions have been made for computing the multiplication constant for reactors with specified core fuel concentrations.
Date: January 26, 1960
Creator: Fowler, T. B.
Item Type: Refine your search to only Report
open access

Acid Formation in the Radiolysis of Phosphorus Esters

Description: The radiolytic decomposition of tributyl phosphate has been show by burr to product gases, acids, and polymers. the acids that are formed can limit the usefulness of tributyl phosphate for the processing of radioactive materials. The study of acid formation on radiolysis therefor becomes important to us for the understanding of the mechanism of acid formation, the influence of added materials and the effect of the structure of organo- phosphorous compounds. Samples of purified esters have been … more
Date: April 3, 1957
Creator: Baldwin, W. H.
Item Type: Refine your search to only Report
open access

Activities in Process Water

Description: The recycling of the process water through the active region of the reactor produces radioactivity in the process water. The source of this radioactivity if (1) activation of dissolved salts in the water, (2) activation of the water itself, (3) activation of the corrosion products, (4) corrosion of active meta and (5) metal recoils from the surface of the reactor. After processes to reduce the radiation level, the activity discharged to the river amounts to 0.468 micro-curie per liter. This all… more
Date: April 7, 1947
Creator: Farmer, W. S.
Item Type: Refine your search to only Report
open access

After Shutdown Cooling Requirements in the HFIR

Description: In order to insure against damage to the reactor in the event of a power failure, it is recommended that emergency forced circulation be provided for a period of about one hour after shutdown. After about one day's decay time, natural circulation cooling on the outside surface of a single fuel annulus should provide sufficient cooling to prevent meltdown. Maximum possible heat up rates at shorter decay times are indicated.
Date: July 20, 1961
Creator: Winters, C. E.
Item Type: Refine your search to only Report
open access

The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes

Description: The method is based on caustic precipitation and centrifugation (which removes the Cs and small amounts of Sr, rare earths, Zr, Nb, and Ru). These are removed in the supernatant and run through a cation exchange column. This separates Zr-NB and Ru. The effluent is precipitated and the Zr-Nb is stored in an asphalt pit. The Ru then may be recovered from the precipitate. The precipitate from the original centrifugation is calcined, pressed and transported to a deep well.
Date: January 17, 1957
Creator: Higgins, I. R.
Item Type: Refine your search to only Report
open access

Analysis of Delayed Neutrons

Description: Calculations for analysis of delayed neutrons. A delayed neutron is a neutron released not immediately during a nuclear fission event, but shortly afterward—ranging from milliseconds to several minutes later. These neutrons are emitted by excited daughter nuclei of certain beta-decaying fission products. Delayed neutrons are critically important for controlling nuclear reactors. Their delayed appearance allows for a slower, more manageable response in reactor power changes, significantly enhanc… more
Date: January 28, 1947
Creator: Stevens, H. E. Jr. & Simpson, J. W.
Item Type: Refine your search to only Report
open access

Analysis of HRT Behavior

Description: This report, published for distribution by the Oak Ridge National Laboratory, outlines the methods being used in attempts to establish a mechanism which will account for the fluctuations observed in the power trace of the HRT.
Date: March 13, 1961
Creator: Kasten, Paul R. & Tobias, Melvin L.
Item Type: Refine your search to only Report
open access

Analysis of Neutron Pulses in a Godiva-Type Reactor

Description: Some calculations have been made to estimate the characteristics of a neutron-burst type fast reactor similar to Godiva but made up of relatively small component parts--the so-called "layered assembly." One spherical and three cylindrical assemblies have been considered. Critical masses, assuming 5% voids, range from 58 to 65 kg of 93.4% enriched U/sup 235/. For a reactivity addition of 0.33 dollars above prompt critical bursts between 2 x 10/sup 17/ and 6.7 x 10/ sup 17/ fissions were computed… more
Date: February 25, 1959
Creator: Nestor, C. W. & Tobias, Melvin
Item Type: Refine your search to only Report
open access

Analysis of UN Solutions for Na

Description: A comparison is presented of results obtained by flame-photometric procedure and spectrographic analysis of samples of UO3 dissolved in HNO3 with various known amounts of NaCl solution added. Results were calculated on the basis of parts per million of U. Results indicate flame-photometric procedures are probably satisfactory for analysis for Na but results obtained using the spectrograph were found low.
Date: September 25, 1952
Creator: Reilly, V. J.
Item Type: Refine your search to only Report
open access

Anisotropic Elastic Scattering of Neutrons

Description: In an elastic collision the neutron loses part of its kinetic energy to the nucleus with both the kinetic and momentum of the system being conserved. However, for many elements the scattering is not isotropic in the center-of-mass system at the higher neutron energies. Many of the present reactor multigroup codes include anisotropic scattering at the high neutron energies, while many others assume isotropic scattering at all energies. In order to consider some of the effects of including anisot… more
Date: March 21, 1957
Creator: Copenhaver, C. M.
Item Type: Refine your search to only Report
open access

Apparent Copper Rate Constants Determined In In-Pile Loop Experiment L-2-22

Description: The results of radiolytic gas pressure measurements in the pressurizer of in-pile loop experiment L-2-22 were used to calculate the copper rate constants in the several different test solutions. Values for the copper concentration obtained from solution analyses were combined with the solution rate constants to determine the apparent molar rate constant for each solution at 280'C.
Date: March 23, 1960
Creator: Jenks, G. H. (Glenn Herbert), 1916- & Baker, J. E.
Item Type: Refine your search to only Report
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