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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

[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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Absorption of Radiation from an "S" Slug by Lead : Final Report Problem Assignment No. TX13-5

Description: The decay of an X (natural uranium) slug, that had been in the pile for 3 years at an average flux of 2.79 x 10(11) n/(cm2)(sec.), has been followed for 150 days through various thicknesses of lead. The activity at one meter, as mR per house per watt, is plotted versus decay time. Absorption curves are given for several decay times. A comparison is shown between experimental and theoretical values.
Date: May 1948
Creator: Ascoli, G. & Sisman, O.
Item Type: Refine your search to only Report
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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

Additional Miscellaneous Tools in the HRT Core

Description: This memorandum presents a description of several additional miscellaneous HRT core maintenance tools, not in an earlier report (1). These tools were used in the removal of the cut up diffuser plates, probing the core wall, gauging the size of the holes, and other simple tasks. Function, design, and operation are described for the following items.
Date: September 26, 1960
Creator: Holz, P. P.
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

After Shutdown Heating in the HFIR

Description: After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanen… more
Date: December 29, 1960
Creator: McLain, H. A.
Item Type: Refine your search to only Report
open access

Aging Characteristics of Hastelloy B

Description: Report issued by the Oak Ridge National Laboratory discussing the aging characteristics of the alloy Hastelloy B. Materials, equipment, experimental procedures, and results used to determine the characteristics of the alloy are presented. This report includes tables, illustrations, and photographs.
Date: August 12, 1957
Creator: Clausing, Robert E.; Patriarca, P. & Manly, W. D.
Item Type: Refine your search to only Report
open access

Air Scattering of Co60 Gamma Rays: Theory Versus Experiment

Description: For Co60 source at 15 meters, the air-scattered gamma dose rate predicted by theory is excerpted from ORNL-1575, pp. 167-203. This is compared with experimental measurements for the same source and comparable geometry reported by Convair in CVAC-170T. After applying an appropriate correction for ground scattering as estimated in Mart-55-16T (Convair), the two results are found to be in substantial agreement.
Date: April 17, 1958
Creator: Moran, Rubert S.
Item Type: Refine your search to only Report
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending December 10, 1951

Description: This quarterly progress report details the ongoing research and experiments at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. The first part of this report discusses reactor theory and design. The second part of this report is not included. The third part of this report discusses materials research. The fourth part of this report includes appendixes
Date: March 6, 1952
Creator: Briant, R. C. & Cottrell, W. B.
Item Type: Refine your search to only Report
open access

The Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending August 31, 1950

Description: Technical report outlining various experiments that took place in the Oak Ridge Area Critical Mass Laboratory until August 31, 1950. Experiments took place in categories of critical experiments, experimental engineering, heat transfer, radiation damage, nuclear measurements, reactor physics, ARE reactor design, circulating fuel reactors, and circulating moderator reactors. [From Summary]
Date: December 4, 1950
Creator: Ellis, C. B. & Thompson, W. E.
Item Type: Refine your search to only Report
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1955

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 other 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. The ANP Project is comprised of about 530 technical and scientific personnel engaged in many phases of rese… more
Date: March 12, 1956
Creator: Jordan, W. H.; Cremer, S. J.; Miller, A. J. & Savelainen, A. W.
Item Type: Refine your search to only Report
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