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NACA Research Memorandums
493
NACA Technical Notes
273
Atomic Energy Commission Reports
170
Oak Ridge National Laboratory Reports
152
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138
United States Geological Survey Reports
79
Trace elements investigations report
67
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60
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Semipermanent Freeze Plug Tests for HRT-CP
Five uninsulated semipermanent freeze coils, series connected, can be frozen when submerged in 70 F water with a Freon-11 flow rate of 1.85 gpm at an inlet temperature of -40 F. The refrigeration unit of the HRT-CP is capable of delivering >3 gpm to a similar semipermanent freeze coil system located in Cell C. Therefore the number of F-11 risers required in Cell C of the HRT-CP can be minimized by series connecting this many semipermanent freeze coils where required.
Date:
March 11, 1957
Creator:
Winget, R. H.
Object Type:
Report
System:
The UNT Digital Library
Neutron and Gamma-Ray Attenuation for a Fission Source in Water : Comparison of Theory with LTSF Measurements
Calculations are presented of the fast neutron dose rate, the gamma-ray dose rate, and the thermal neutron flux along the source plate axis in the Lid Tank with the tank filled entirely with water. These calculations are compared with experimental measurements. The calculations are absolute and are compared with absolute measurements.
Date:
March 12, 1957
Creator:
Otis, David Ridgway
Object Type:
Report
System:
The UNT Digital Library
In-Pile Slurry Loop Program
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.
Object Type:
Report
System:
The UNT Digital Library
High-Temperature Properties in Relation to Design
The essential physical and mechanical properties of materials which enter into the design considerations of high-temperature systems have been outlined, and the relationship of these factors to the detailed design of structural members noted. Particular attention is given to the phenomenon of strain-cycling and relaxation, and several engineering devices wherein these effects can markedly influence design are mentioned. Techniques and apparatus for the measurement of strain-cycling and relaxation properties are described and some recent data for Inconel at 1500 F is reported. A brief discussion is presented on design-criterial for high-temperature applications, and it is pointed out that in some high performance devices the considerations of the strain-cycling phenomenon may impose the design philosophy of "steady-state" operation. Some elementary applications of strain cycling data to design are described, and test experience indicates that analytical techniques can be developed for predicting with reasonable reliability of the fatigue life of structures.
Date:
March 14, 1957
Creator:
Weir, J. R.; Meghreblian, Robert V. (Robert Vartan) & Douglas, D. A.
Object Type:
Report
System:
The UNT Digital Library
Comments on the Determination of the Particle Size Distribution of Thorium Oxide
Factors affecting the results of thoria particle size distribution measurements by sedimentation procedures currently and recently employed are considered. The effects of thoria concentration, solvent, dispersant, thoria properties, and other factors are discussed.
Date:
March 31, 1957
Creator:
Moore, G. E.
Object Type:
Report
System:
The UNT Digital Library
TBP Stripping in Bubble-Cap Column and Concomitant Product Evaporation
A study was conducted to demonstrate the stripping and evaporation steps in a Purex-type uranium recovery process and to ascertain the operating behavior of the equipment under a range of conditions. The factors considered were control, effectiveness, and reliability of equipment and optimum feed point. Experimental procedures are described, and recommendations for equipment modifications are included. (J.R.D.)
Date:
March 18, 1957
Creator:
Long, J. T.
Object Type:
Report
System:
The UNT Digital Library
Beryllium
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 engineers with data on the high temperature strength properties of hot-pressed beryllium. In the interim, it will be necessary for the metallurgists and design engineers to make judicious estimates and extrapolations from the data available.
Date:
March 21, 1957
Creator:
Whitman, M. J.
Object Type:
Report
System:
The UNT Digital Library
Measurement of the Friction Characteristics for Flow in the ART Fuel-to-NaK Heat Exchanger
The friction characteristics of a full-scale straight-tube model of the ART fuel-to-NaK heat exchanger were determined experimentally. The presence of the spacers resulted in a transition to semi-turbulent flow at a Reynolds modulus of 350. this semi-turbulent flow persisted up to a Reynolds modulus of 5,000. The circumferential spacers were found to contribute slightly more than the radial spacers to the pressure loss in the heat exchanger.
Date:
March 19, 1957
Creator:
Cohen, S. I. & Jones, T. N.
Object Type:
Report
System:
The UNT Digital Library
In-Reactor Autoclave Corrosion Studies. II, Autoclave Z18
In order to test the effect of chromate ion on the corrosion of Zircaloy-2, a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm of Cr (VI) was autoclaved with rocking at 280 degrees C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presence of Cr (VI) had no significant effect on the radiation corrosion of Zircaloy-2 by enriched uranyl sulfate solutions. However, the data are not conclusive and may be interpreted as showing a low corrosion rate for a limited period (i.e. a short term inhibition) followed by correspondingly rapid corrosion.
Date:
March 22, 1957
Creator:
Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
Object Type:
Report
System:
The UNT Digital Library
Status Report on the Disposal of Radioactive Wastes
The new and as yet unsolved problems introduced by the production of large quantities of fission products and radioactive isotopes from fission or neutron capture present mankind a most complex technical, economic, and political problem. On one hand, the possibility of using the fission process to produce energy from an unexploited and abundant natural source is emerging from large programs of research and development. We are also beginning to see the promise of use of particulate and electromagnetic radiation for the good of man. On the other hand, we are presented with the problem of controlling the dangerous products of fission for periods of time measured in terms of many hundreds of years, periods longer than the effective tenure of any political state in history. We must not only devise ways of protecting ourselves in the present and for our lifetime but, in addition, we must establish the basic technical, social, and administrative control of vast quantities of artificial radioactivity that must remain effective for at least ten to twenty lifetimes.
Date:
June 25, 1957
Creator:
Culler, Floyd L., Jr. & McLain, Stuart
Object Type:
Report
System:
The UNT Digital Library
Section 9.0 to Status Report on the Disposal of Radioactive Wastes
Section 9.0 is the "Chemical Processes for Fission Product Concentration, Removal or Fixation" section of the Status Report on the Disposal of Radioactive Wastes. The report is divided into four areas: (1) Introduction; (2) Summary of waste processes; (3) Concept of a multipurpose waste processing facility; and (4) Details of some of the waste processes.
Date:
September 3, 1957
Creator:
Culler, Floyd L., Jr.
Object Type:
Report
System:
The UNT Digital Library
Source of Fission Products in LITR Cooling Water
A study has been made of the radioactive nuclides present in the cooling water of the Low Intensity Test Reactor. Prominent nuclides which have been identified include Np239 and certain fission products. The experimental evidence points to the probability that there could be adequate U235 contamination on the fuel plates to quantitatively account for the fission products identified in the LITR cooling water. inasmuch as new aluminum does not contain uranium, it must be assumed that the contamination occurs during the fabrication of the fuel elements.
Date:
March 26, 1957
Creator:
Moeller, D. W. (Dade W.) & Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library
Compatibility Tests of Various Materials in Molten Sodium
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.
Object Type:
Report
System:
The UNT Digital Library
Anisotropic Elastic Scattering of Neutrons
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 anisotropic scatting, reference is made t the multigroup equation generally assumed for the slowing-down density.
Date:
March 21, 1957
Creator:
Copenhaver, C. M.
Object Type:
Report
System:
The UNT Digital Library
Radiation Dose Received by Passengers and Crew on Planes Carrying the Maximum Number of Radiation Units
The dose of ionizing radiation received by passengers and crew members traveling on commercial airlines which transport radioisotopes is of interest to all persons who travel the airways frequently. Tariff regulations permit the air transport of 40 units of radioactive materials where one unit represents a quantity of radioisotopes which when packaged delivers a dose rate of one mr/hr at a distance of one meter from the center of the package. Using five different types of commercial aircraft, shipments of radioisotopes were simulated and dose levels determined at various locations in the aircraft under conditions normal to commercial travel. The survey indicates that the tariff regulations should be amended giving consideration to the type of aircraft involved.
Date:
March 1, 1957
Creator:
Davis, D. M.; Hart, J. C. & Warden, A. D.
Object Type:
Report
System:
The UNT Digital Library
Effects of Heat Treatment on Microstructure and Fabricability of 48 wt % Uranium - 52 wt % Aluminum Alloys
It has been reported in the literature that prolonged soaking of 16 wt & uranium-aluminum alloys at elevated temperatures induces a microstructural changed termed "conglobulation". this process is essentially a spheroidization of the UAl4 eutectic. Conclusions of the tests: (1) Extended soaking of 48 wt $ uranium-aluminum alloy billets at 600 C does not improve their hot-rolling characteristics. (2) Soaking periods of 50 hours and greater reduce the tensile and yield strengths of these alloys. (3) Soaking for 50 hours results in complete spheroidization of the eutectic in 48 wt % uranium-aluminum alloys.
Date:
March 15, 1957
Creator:
Thurber, William C.
Object Type:
Report
System:
The UNT Digital Library
Acid Formation in the Radiolysis of Phosphorus Esters
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 irradiated in the ORNL cobalt source. Conclusions: (1) The formation of acid from tributyl phosphate during irradiation with cobalt gamma rays involves a mechanism that is not a primary step. Evidence has been obtained for a secondary reaction that is minimized by the presence of certain compounds. (2) Toluene acting as an inhibitor for radiolytic formation of acid may indicate the usefulness of an aromatic hydrocarbon diluent in processing. (3) The aromatic hydrocarbon, when phenyl, was not effective when it was part of the molecule. (4) First tests revealed that dibutyl butyl-phosphonate produced less acid the TBP and may warrant further consideration for process application.
Date:
April 3, 1957
Creator:
Baldwin, W. H.
Object Type:
Report
System:
The UNT Digital Library
Suggestion for High Pressure Letdown Device
A letdown valve design is described which reduces erosion of the sealing surfaces. It also provides for water flushing of the sealing surface before closing.
Date:
April 2, 1957
Creator:
Lyon, Richard Norton
Object Type:
Report
System:
The UNT Digital Library
Pressure Rise in HRT Shield Due to Reactor and Replacement heat Exchanger Rupture
.Recalculations were made of HRT cell pressures in the event of a simultaneous rupture of the reactor core vessel and the fuel and blanket heat exchangers. These calculations will be applicable after the replacement fuel heat exchanger is installed. The pressure rise in the cell is plotted as a function of time. A maximum cell pressure of 34 psig is achieved ~7 sec after rupture.
Date:
April 2, 1957
Creator:
Bolger, J. C.; Maak, R. O. & Gift, E. H.
Object Type:
Report
System:
The UNT Digital Library
A Preliminary Study of Molten Salt Power Reactors
A preliminary study of molten salt power reactors was made. The most promising fuel carrier salts were the fluorides and chlorides of the alkali metals, zirconium, and beryllium. The chlorides were found to have lower melting points but were less stable and more corrosive than the fluorides. A Li/sup 7/ F- - BeF/sub 2/ mixture with ThF/sub 4/ and UF/sub 4/appeared to perform best. Of the numerous alloys tested as container material, Inconel and a nickel-- molybdenum alloy INOR-8 appeared to be the most resistant to corrosion. To study the performance, safety, economics, and construction costs of a typical molten salt reactor, a reactor of specific type and size was chosen for study. The reference design reactor was a two-region homogeneous converter with a core salt of 70 mole% Li/sup 7/F and 30% BeF/sub 2. ThF/sub 4/ and enough VF/sub 4/ for criticality were added. Study indicated that a molten salt reactor would produce economical power, but the problem of developing a salt core and a container metal which would last for many years of operation needed further study. (M.C.G.)
Date:
April 29, 1957
Creator:
MacPherson, H. G.; Alexander, L. G.; Carrison, D. A.; Estabrook, J. Y.; Kinyon, B. W.; Mann, L. A. et al.
Object Type:
Report
System:
The UNT Digital Library
Second and Third Operating Test of HRT Core Vessel Transition Joint and Expansion Bellows Mockup
Second and third tests were conducted on an expansion bellows and Zircaloy-stainless steel transition joint assembly, duplicating that used in the core-pressure vessel assembly of the HRT. The assembly was exposed for 1140 hours in the second test and and 167 hours in the third to a solution containing 0.04m UO2SO4, 0.02m H2SO4, and 0.005m CuSO4 in a 100A dynamic corrosion loop under conditions simulating reactor startup, shutdown, and steady-state operation. Results indicated that the transition joint assembly as tested was mechanically sound and leak-tight. Pit-type corrosion continued on the expansion bellows where the upper retaining tangent contacts the bellows. Results are included of specimens exposed to the circulation solution during transition joint and bellows test.
Date:
April 30, 1957
Creator:
Greeley, R. S.; Ulrich, W. C.; Savage, H. C.; Griess, J. C. & Mauney, T. H.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report of the Solution Corrosion Group for the Period Ending April 30, 1957
A third test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel was completed. No additional mechanical deflections of the bellows were made, but 12 additional thermal cycles of the unit were carried out. . The joint and bellows functioned properly and were leak-tight. Corrosion of stainless steel in 0.04 m UO2SO4 containing equimolar beryllium sulfate was not greater at 10-15 fps and much less at 15-75 fps, than in HRT solution at 200 and 225 C. Increasing the beryllium sulfate concentration to 0.08 m increased corrosion at 225 C and resulted in an unstable solution at 300 C.
Date:
April 30, 1957
Creator:
Griess, J. C.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Object Type:
Report
System:
The UNT Digital Library
Curve Plotting Routine for the Oracle
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.
Object Type:
Report
System:
The UNT Digital Library
Supplement to: Curve Plotting Routine for the Oracle (57-4-56)
A general program has been written to plot curves on the Oracle curve plotter. The supplement includes changes to slow down some of the loops and minimize the possibility of read-around errors and changes to handle special cases.
Date:
October 22, 1957
Creator:
Lietzke, M. P.
Object Type:
Report
System:
The UNT Digital Library