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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.
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.
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.
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.
open access

Applied Health Physics Semi-Annual Report : July 1956 - December 1956

Description: This semi-annual report of the Applied Health Physics Section of the Health Physics Division provides both narrative and quantitative descriptions of area air monitoring activities, fallout activity, rain water analyses, Clinch River and White Oak Creek analyses, background radiation monitoring, and monitoring of the work and protective garments laundry. Measurements for gamma and beta activity are reported in millicuries/cubic centimeter. The report does not provide information on specific rad… more
Date: 1957
Creator: Oak Ridge National Laboratory. Health Physics Division
open access

APPR-1 Type Absorber Rod Irradiation Test -- Irradiation Request ORNL MTR-29

Description: In order to evaluate the behavior of an APPR type absorber rod, an irradiation test program has been established. Approximately 21 more samples are planned for testing under this request. The request proposes testing a full size APPR-1 type control rod in the MTR. The objective of the test is to better evaluate the neutron absorbing material proposed for the APPR-1 control rod.
Date: January 4, 1957
Creator: Gross, E. E. & Schaffter, L. D.
open access

Bellows Failure in Solids Separation Loop of the HRT Mockup

Description: The failure of the valve bellows would appear to be due to a combination of stress corrosion and crevice corrosion. Stress corrosion occurred as evidenced by the transgranular branched cracking found in the bellows and in the base which which was joined to the bellows. It seems probable that chlorides were present, which, along with the residual stresses present in the bellows assembly, created the necessary conditions for stress corrosion to occur. Crevice corrosion occurred probably due to he… more
Date: February 5, 1957
Creator: Kegler, T. M., Jr. & Hammond, J. P.
open access

Beryllium

Description: The information concerning beryllium assembled herein has been selected primarily to provide information that might be pertinent to the design of the ART. The creep-rupture data in the literature have been obtained from vacuum cast and extruded beryllium, rather than from the hot-pressed beryllium which will be used in the ART. A research program is being conducted by the Brush Beryllium Company, under contract to the Oak Ridge National Laboratory, which will eventually provide the design engi… more
Date: March 21, 1957
Creator: Whitman, M. J.
open access

Calculation of Shield Induced Gamma Radiation Escaping Through Openings in a Biological Shield -- Application to the HRT

Description: A method was developed for calculating shield induced gamma radiation escaping through openings in a biological shield. The method was applied to the HRT and the results indicated that the contribution to the dose from induced activity in the HRT shield was around 0.1 r/hr and was insignificant in comparison to to other mechanisms contributing to the escape of gamma rays through shield openings.
Date: January 11, 1957
Creator: Claiborne, H. C. & Fowler, T. B.
open access

Calculation of Wall-Scattered Gamma Radiation Escaping through a Shield Opening - Application to the HRT

Description: A simplified method was developed for calculating wall-scatter gamma radiation escaping through a shield opening. The method was applied to the HRT and the results showed that next to the line of sight contribution, scattering of the wall of the shield opening was the main contribution to the dose at the rear edge of the shield. Design charts were prepared that give the dose as a function of the gamma source location with the reactor cell.
Date: February 19, 1957
Creator: Claiborne, H. C. & Fowler, T. B.
open access

Carbon Steel in High Temperature Water

Description: Resistance of carbon steel to corrosion in oxygenated high-temperature (250C) water was unexpectedly good at high oxygen concentration. Pertinent literature, critically examined, and toroid experiments indicted that at low oxygen concentration attack did increase with concentration, but as oxygen concentration was sufficiently increased, more protective films were formed on the metal. Some corrosion factors in the application of carbon steel to nuclear reactors systems are discussed.
Date: January 31, 1957
Creator: Moore, G. E.
open access

Catalysts for Recombination of Radiolytic Gases Over Thorium Oxide Slurries

Description: Catalysts for use in recombining the gases produced by the radiolytic decomposition of water in thorium oxide slurries under neutron irradiation were investigated in out-of-pile tests using stoichiometric mixtures of hydrogen and oxygen. Most favorable results were obtained with a molybdenum oxide catalyst. Satisfactory rate also were attained with palladium and silver oxides. Copper, nickel, vanadium and chromium compounds were less effective.
Date: January 29, 1957
Creator: Morse, L. E.
open access

The Chemical Processing of Two-Region Aqueous Homogenous Reactors

Description: A promising scheme for the chemical processing of a thorium breeder reactor of the two-region aqueous homogeneous type consists of the following operations: concentration of insoluble fission and corrosion products from the core system into a small volume of fuel solution, combining this slurry with irradiated thorium oxide slurry taken from the blanket, recovery of D2O by evaporation, dissolution of the thorium and uranium in HNO3, and, after a suitable cooling period, recovery of the uranium … more
Date: January 29, 1957
Creator: Ferguson, D. E.
open access

The Choice in Thorium Oxide Slurries for the Prevention of Caking in Circulating Systems

Description: A qualitative theory for cake formation in ThO2 slurries is presented. The sphere formation which occurs in "Standard" slurry can be explained on the same basis. The irregular and unpredictable yield strength is easily fitted into the theory. On the basis of this theory, the writer has been led to the conclusion that only colloidally stable slurries, or slurries with crystallites or comminution-resistant particles which are large enough to overcome colloidal effects (probably larger than 0.1u) … more
Date: April 22, 1957
Creator: Lyon, R. N.
open access

Compatibility Tests of Various Materials in Molten Sodium

Description: Several compatibility test of various materials in contact in sodium under 500 psi pressure were conducted for 716 hr at 1500 F. Of the diffusion couples studies, the Inconel-beryllium system showed the largest amount al alloying. The reaction between molybdenum and beryllium resulted in the formation of two compounds, both of which were severely cracked in several areas. The molybdenum-INOR #8, and the INOR #8p type 316 stainless steel interfaces showed little if any alloying.
Date: March 25, 1957
Creator: Carlander, R. & Hoffman, E. E.
open access

Control System for HRT Cooling Water

Description: The circuits described herein and shown functionally in Fig. 1 are to be added to the HRT control circuit to provide control and protection for the revised HRT cooling water system. The circuitry will provide protection against excess pressure in the demineralized cooling water loop and cooling water activity, will initiate action to insure containment of activity in event of an explosion and will provide emergency cooling water from the tower basin when required.
Date: February 11, 1957
Creator: Moore, R. L.
open access

Cracks in HRT Flange Bolts and Ferrules

Description: When it was discovered that two HRT flange bolts of a lot of 16 spares contained serious cracks, a program was launched to (1) determine the cause for the cracking, and (2) find methods for non-destructive testing the remainder of the 672 bolts shipment, a large portion of which had been installed in the HRT. Concurrently, inspection of 8 ferrules removed from an HRT flange revealed hairline cracking in 4 of them. Magnaglo, a magnetic particle inspection method using a fluorescent dye, proved t… more
Date: January 29, 1957
Creator: Hammond, J. P.; Adamson, G. M. & Kegler, T. M., Jr.
open access

Cross Section Program at ORNL

Description: Short reports to the members of the Nuclear Cross Section Advisory Group from three groups: (1) High voltage group; (2) Fast chopper time-of flight spectrometer; and (3) Electronuclear research division.
Date: January 21, 1957
Creator: Harvey, J. A. & Fowler, J. L. (Joseph L.)
open access

Curve Plotting Routine for the Oracle

Description: A general program has been written to plot curves on the Oracle curve plotter. A description of the code and complete instructions for preparation of input tapes and operation of the code are given. The code tape is available from the Mathematics Panel or from the author.
Date: April 11, 1957
Creator: Lietzke, M. P.
open access

Delay Time Prior to Dumping the HRT

Description: Some refined calculations have been made, relative to a proposed delay prior to a dump, to determine the expected D2 concentration in the vent stream from the pressurizer gas bleeds during a dump of the Homogeneous Reactor Test (HRT). These calculations indicate that for vent valves have a Cv of 0.07 (venting time from 2000 psia to D2O saturation pressure of approximately 12 minutes), a delay period is not required since the D2 concentration is well below lower explosive limit. For vent valves … more
Date: January 10, 1957
Creator: Gift, E. H. & McLain, Howard A.
open access

Determination of Submicron Particle Sized by an Activation Analysis - Centrifugation Method

Description: The feasibility of determining particle sizes in the submicron range by employing an activation analysis - centrifugation method has been demonstrated. It is believed that this method is now applicable to the analysis of thorium oxide for submicron particles. The same techniques are, in most instance, usable in determining particle sized in other sample materials.
Date: January 29, 1957
Creator: Bate, L. C. & Leddicotte, G. W.
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