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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
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
0-2 kv Flash Tube Supplies
In order to perform the various experiments with a bubble chamber, a high intensity flash tube is used. This report briefly describes the power supplies designed and constructed to power these lamps.
Date:
March 15, 1962
Creator:
Miller, D. M.
Object Type:
Report
System:
The UNT Digital Library
Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores
A series of two-group calculations has been made on the Oracle for the purpose of obtaining critical-mass and flux distribution data for various ORR core configurations. The 3G3R code of Bate, Einstein, and Kinney was used, together with the RSP code developed by Nelson. This made it possible to obtain results for the three-dimensional case. The results, which are presented graphically, are intended to serve as a guide for the design of experiments until such time as actual measurements are available. The calculations were performed for the "clean cold" case, and it should be realized that the presence in the core of experiments and of fission products built up during operation will materially alter the flux patterns found. It is believed that the critical-mass data are accurate to within 10%. Within the fuel region it is believed that the thermal-flux patterns are the also accurate to this degree. Comparison of the results with MTR critical experiments, however, indicates that the thermal flux in the reflector in the vicinity of the fuel-reflector interface may have been underestimated by a factor of as much as 1.3. It should also be recalled that in a two-group calculation the "fast flux" is often a …
Date:
March 11, 1958
Creator:
Binford, F. T.
Object Type:
Report
System:
The UNT Digital Library
Experiments on the Release of Fission Products from Molten Reactor Fuels
Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types, have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of rare gases, iodine, bromine, cesium, and rubidium. In the presence of air or water vapor, strontium and other fission products are not released. At trace concentration of fission products, slow melting of the APPR plate at 1525 C in air or steam effected the release of 50% of the rare gases, 33% of the iodine, 9% of the cesium, and traces of strontium. After 25% burn-up, the cesium value increased to about 60%. Aluminum alloy of the MTR type, also at trace concentration, upon melting at 700 C released up to 2% of the iodine, 10% of the rare gases, and negligible portions of other fission products. Zirconium alloy of the STR type after 15% burn-up, when melted at 1850 C, released up to 95% of the rare gases, 90% of …
Date:
March 11, 1958
Creator:
Parker, George W. & Creek, George E.
Object Type:
Report
System:
The UNT Digital Library
In-Reactor Autoclave Corrosion Studies II : Autoclave Z-19
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 Cr (VI) was autoclaved with rocking at 280 C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the a 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 a 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