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Statistical Evaluation of Methods for the Analysis of Dibasic Aluminum Nitrate (DIBAN)

Description: The indicated methods for determining the following constituents of Diban, which is an aqueous solution of dibasic aluminum nitrate, Al(OH)2NO3, were evaluated statistically: 1aluminum by gravimetric, volumetric, and spectrophotometric procedures, 2. basicity (hydroxyl value) by formation of an aluminum complex and titration of the free acid with standard alkali solution, 3. total nitrogen by the Kjeldahl method, 4. ammonia by the Kjeldahl method, and 5. nitrates by means of a cation-exchange r… more
Date: September 16, 1955
Creator: Surak, J. G.; Thomason, P. F. & Haaen, H. P.
Partner: UNT Libraries Government Documents Department
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The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates

Description: Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after ir… more
Date: September 7, 1955
Creator: Carrell, R. M.
Partner: UNT Libraries Government Documents Department
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ORNL Metal Recovery Plant Processing Clementine Reactor Fuel Elements: Terminal Report

Description: This report presents data obtained from processing 33 Clementine Reactor fuel elements in the ORNL Metal Recovery Plant to recover approximately 15 kg of plutonium and 0.16 g of americium.
Date: September 7, 1955
Creator: Matherne, J. L.; Brooksbank, R. K.; Campbell, D. O.; Chandler, J. M.; Rylton, C. D.; Leuse, R. E. et al.
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report for Period Ending August 31, 1955

Description: LITR Fluoride-Fuel Loop. — The inconel loop was dismantled for removal of the samples and for recovery of the uranium by using the remote cutting tools installed in a half cell of the Solid State Building. Disassembly proceeded without incident. An electric-arc cutting technique was developed for removal of the stainless steel enclosure around the pump bowl. Fission power and maximum flux were determined by irradiating a simulated loop, by heat-balance calculations, by radiochemical analyses fo… more
Date: November 16, 1955
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
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Determination of Corrosion Products and Additives in Homogeneous Reactor Fuel III. Polarographic Determination of Iron(III)

Description: An ion-exchange -- polarographic method was developed for the determination of iron(III) in Homogeneous Reactor Fuels. Copper, which interferes, is removed from the fuel by plating it onto a cadmium coil. Iron is oxidized to iron(III) by potassium permanganate, and the iron(III) is separated from interfering metal ions by ion exchange on a Dowex 1 resin column that is in the sulfate form. The iron(III) in the effluent is determined polarographically in 0.5 M sodium citrate solution as supportin… more
Date: October 24, 1955
Creator: Horton, A. D.; Thomason, P. F. & Raaen, H. P.
Partner: UNT Libraries Government Documents Department
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The Influence of End Mirrors, High Density and Long Tube Length on Radial Diffusion

Description: Diffusion in an arc plasma across a magnetic field is investigated. The geometry is similar to that reported in ORNL-1890 but with the addition of magnetic mirrors on the ends of the arc chamber. It is shown that mirrors do not eliminate the "short circuit" effect. Comparison of the e-folding length, rₒ, of the radial ion density with and without mirrors, affords a direct measurement of ℓ/λ where ℓ is the arc length and λ the mean-free-path. In addition rₒ is independent of gas pressure with mi… more
Date: September 22, 1955
Creator: Simon, Albert
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry Division Semiannual Progress Report For Period Ending October 20, 1955

Description: The development of ionic methods for the determination of corrosive products in the highly radioactive Homogeneous Reactor (HR) fuels has been of major interest in the work of the Ionic Analyses Laboratory. Methods for the spectrophotometric determination of aluminum and for the polarographic determination of iron in HR fuels have been developed. The polarographic determination of molybdenum in uranyl sulfate solutions was studied. A polarographic method for the determination of zinc was develo… more
Date: December 27, 1955
Creator: Kelley, M. T.; Susana, C. D. & Rooen, H. P.
Partner: UNT Libraries Government Documents Department
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Relative Biological Hazards of Radiations Expected in Homogeneous Reactors TBR and HPR

Description: An evaluation of the relative health hazards of radioisotopes produced in nuclear reactors is reported. The most important hazards were indicated to be I131, the Sr90 - Y90 chain, the Ce144 -Pr144 chain, Sr 89, the Ba140-La40 chain, Y91, the Zr95-Nb95 chain, Pr143, La140 , and Pa233. The most critical body organs affected by air-borne contamination are the thyroid gland, the bone marrow, the lungs, and the gastrointestinal tract. Where possible, continuous daily removal of gaseous and solid fis… more
Date: December 2, 1955
Creator: Arnold, E. D. & Gresky, A. T.
Partner: UNT Libraries Government Documents Department
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Determination of Trivalent Uranium with Methylene Blue

Description: A direct titrimetric method for the determination of trivalent uranium in uranium trifluoride and mixtures of fused fluoride salts was developed. The method is based on the stoichiometric oxidation of trivalent uranium to the tetravalent oxidation state with an acidic solution of methylene blue. The sample containing trivalent uranium is dissolved at room temperature in an excess of standard methylene blue solution in a carbon dioxide atmosphere; the excess oxidant is variation of the method is… more
Date: November 22, 1955
Creator: Ross, W. J.; Meyer, A. S.; White, J. C.; Kelley, N. T. & Susano, C. D.
Partner: UNT Libraries Government Documents Department
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ORNL Mortal Recovery Plant: Processing of ORNL Graphite Reactor Fuel Elements During the Period July and August, 1955

Description: From July 7 to August 31, 1955, 20 tons of uranium and 1,200 g of plutonium were recovered in 47 days of plant operation at an average rate of 833 lb/day of uranium and at a cost of $2.60/lb of uranium. Uranium and plutonium recoveries were, respectively, 99.9 and 95.5 per cent.
Date: November 11, 1955
Creator: Brooksbank, R. E.; Chandler, J. M. & Hylton, C. D.
Partner: UNT Libraries Government Documents Department
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Preliminary Results of APPR Critical Experiments, Part I.

Description: This memorandum is the first in a series reporting progress in the program of critical experiments in the ORNLArmy Package Power Reactor Project. The critical assembly, designated as CA-25, is analogous to the APPR design core and consists of 45 fuel boxes, in a 7 x 7 array with the corners removed, contaIned in a large water tank. Two sides of each box are slotted for the insertion and positioning of any desired loading of eighteen plates of fuel, structural material, and poison. The array is … more
Date: November 25, 1955
Creator: Williams, D. V. P.
Partner: UNT Libraries Government Documents Department
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Stable Isotope Research and Production Division Semiannual Progress Report

Description: The Spectroscopy Research Laboratory is concerned with research and development in the fields of nuclear magnetic resonance, microwaves, infrared and optical spectroscopy, spectrochemistry, and x rays. Research is directed toward fruitful methods of isotope analysis; new element and compound analytical methods having application to immediate Laboratory or long-range commission needs; and fundamental research on isotopes, elements, and compounds. The work is reported on a project basis to give a… more
Date: February 18, 1955
Creator: Keim, C. P.
Partner: UNT Libraries Government Documents Department
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Aircraft Reactor Test Hazards Summary Report

Description: The successful completion of a program of experiments, including the Aircraft Reactor Experiment (ARE), has demonstrated the high probability of producing militarily useful aircraft nuclear power plants employing reflector-moderated circulating-fuel reactors. Consequently, and accelerated program culminating in operation of the Aircraft Reactor Test (ART) is under way. In order to adhere to the compressed schedule of the accelerated program, it is essential that the Atomic Energy Commission app… more
Date: January 19, 1955
Creator: Cottrell, W. B.; Ergen, W. K.; Fraas, A. P.; McQuilkin, F. R. & Meem, J. L.
Partner: UNT Libraries Government Documents Department
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Mathematics Panel Semiannual Progress Report

Description: From July through December, a total of 1750 hr of computer time was used by programmers in "debugging" and in running problems. With the acquisition of a second operator, the evening shift was initiated. A night-shift operator is presently being trained, and third-shifts operations will probably begin after completion of the magnetic-tape memory. / Engineering time is regularly scheduled for 4 hr each morning and 1/2 hr late in the afternoon. An electronic technician is on duty during evening-s… more
Date: March 2, 1955
Creator: Householder, A. S. & Sangren, W. C.
Partner: UNT Libraries Government Documents Department
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Homogenous Reactor Project Quarterly Progress Report For Period Ending January 31, 1955

Description: The reactor equipment cell is expected to be completed by February 15. While filled with water, the tank was inspected for leaks, and the few leaks found will have been repaired by February 15. All orders for construction materials placed prior to this quarter have been received. New requisitions issued during the quarter total $16,000. Work orders were issued, and fabrication of all low-pressure-system components was begun in the ORNL shops. The thermal shield around the reactor vessel was spe… more
Date: April 6, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
Partner: UNT Libraries Government Documents Department
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Electronuclear Research Division Semiannual Progress Report For Period Ending March 20, 1955

Description: The ORNL 86-in. cyclotron is being modified to provide for deflection of the proton beam. It is expected that operation will be resumed late in the spring. Nuclear physics work was limited, for the most part, to interpretation of previously collected data and to making preparations for utilizing the deflected beam. It was found that for certain isotopes the production rates could be almost doubled by operating at a slightly reduced energy and a much larger current. With the use of the ORNL 63-i… more
Date: June 24, 1955
Creator: Livingston, Robert S. & Howard, F. T.
Partner: UNT Libraries Government Documents Department
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Determination of Corrosion Products and Additives in Homogenous Reactor Fuel II. Polarographic Determination of Chromium

Description: A satisfactory ion-exchange-polarographic method was developed for the determination of either chromium(VI) or total chromium in Homogeneous Reactor fuels. Total chromium is determined as chromium (VI) , i.e., chromate, and in the same way as is chromium(VI), after chromium in the lower valence states is oxidized to chromate by potassium permanganate. Chromate is separated from all interfering metal ions in the fuel by ion exchange on a Dowex 50 resin column. The Chromate in the effluent is det… more
Date: September 13, 1955
Creator: Horton, A. D. & Thomason, P. F.
Partner: UNT Libraries Government Documents Department
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Homogenous Reactor Project Quarterly Progress Report For Period Ending April 30, 1955

Description: Part I. Experimental Reactors: The effect of prompt-neutron lifetime upon reactor safety was investigated for the HRT. It was found that for a given pressure rise the allowable rate of reactivity addition was relatively insensitive to the average prompt-neutron lifetime, although the rate de creased somewhat with decreasing lifetime for the higher pressure rises. With only source neutrons present and the reactor initially subcritical, the allowable rate was practically independent of the initia… more
Date: July 14, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
Partner: UNT Libraries Government Documents Department
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The Extraction and Recovery of Uranium (and Vanadium) from Acidic Liquors with DI (2-Ethylhexyl) Phosphoric Acid and Some Other Organophosphorus Acids

Description: Bench scale studies have been made of the recovery of uranium from acid leach liquors (and slurries) by solvent extracting with di (2-ethylhexyl) phosphoric acid in an organic diluent. Uranium may be stripped from the organic solvent by either alkaline or acidic reagents, the former having been studied in greater detail. On the basis of these tests, a recovery process may be considered which shows promise both from the standpoint of operation and chemical costs. Under proper conditions, vanadiu… more
Date: May 13, 1955
Creator: Blake, C. A.; Brown, K. B.; Coleman, C. F.; Horner, D. E. & Schmitt, J. M.
Partner: UNT Libraries Government Documents Department
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Physics Division Semiannual Progress Report, September 10, 1955

Description: Report containing papers, publications, and announcements from the Physics Division of the Oak Ridge National Laboratory.
Date: 1955~
Creator: Oak Ridge National Laboratory. Physics Division.
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report, August 30, 1955

Description: Report containing papers, publications, and announcements from the Solid State Division of the Oak Ridge National Laboratory.
Date: 1955~
Creator: Oak Ridge National Laboratory. Solid State Division.
Partner: UNT Libraries Government Documents Department
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A Cost Analysis of the Idaho Chemical Processing Plant

Description: A capital cost breakdown of the Idaho Chemical Processing Plant, a directly maintained remotely operated plant for processing spent enriched uranium fuel assemblies from reactors, is presented. The capital investment in the plant, including design, construction, training, and preoperational costs, an estimate of the direct costs incurred by the Atomic Energy Commission, and a proportional part of the costs of Central Facilities, including the value of the land and improvements theorem when acqu… more
Date: January 4, 1955
Creator: Robertson, P. L. & Stockdale, W. G.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report for Period Ending July 31, 1955

Description: Construction of the HRT reactor shield tank was completed, and the inside surfaces were painted. The roof structure for the tank is being assembled in preparation for an acceptance pressure test. Service piping and instrument lines are being installed in the central room area by ORNL craft forces. This work is approximately 50% complete. Fabrication of all temperature system components, except the blanket outer storage tanks, has been completed.
Date: October 10, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
Partner: UNT Libraries Government Documents Department
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