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Status Report on the Disposal of Radioactive Wastes

Description: 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 electroma… more
Date: June 25, 1957
Creator: Culler, Floyd L., Jr. & McLain, Stuart
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Fluctuations in the Widths on Neutron Reaction Cross Sections

Description: The general Wigner-Eisenbud theory is used to develop a method of analysis for the cross sections of fissionable nuclei. The method is employed in giving a reasonable description of the low energy cross sections in U/sup 235/. The single level fit for U/sup 235/ is known to be unreasonable. Many level expressions for the cross sections are derived--the only approximation to the general theory being the neglect of all but a small group of resonances. It is shown that regardless of the number or … more
Date: June 1, 1957
Creator: Dresner, Lawrence
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operating Instructions for the UNIVAC Program OCUSOL-A : a Modification of the Eyewash Program

Description: The Eyewash program, written by James H. Alexander and Nancy D. Given, provides solutions of reactor criticality problems in spherical geometry by means of the group diffusion method. It employs thirty lethargy groups (plus one thermal group) in nine regions. The input consists principally of specifying the geometrical scaling factor, boundaries and compositions of the various regions, and temperature level. The output includes the value of vc that would render the system critical, the relative… more
Date: June 5, 1957
Creator: Alexander, L. G.; Carrison, D. A.; Roberts, J. T. & Van Norton, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cross Sections for OCUSOL-A Program

Description: The OCUSOL-A program (ORNL-CF-57-6-4) for Univac is a modification of the Eyewash (ORNL-1925) multi-group, multi-region reactor code. The group=energy-lethargy-temperature relationship are given in Table A. The element code numbers are given in Table B. The cross sections now on the sigma-tape are given in tables in the Appendix numbered with the element code number. This technical report explains the bases for choosing the cross sections.
Date: June 11, 1957
Creator: Roberts, J. T. & Alexander, L. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Slurry Physical Properties on Heat Exchangers and Pump Characteristics

Description: Design calculations were made for a system consisting of a pump, one hundred feet of pipe, and a heat exchanger to remove 1 Mw of heat from various aqueous thorium oxide slurries. The rheological properties of the slurries were varied over a range of yield stresses from 0 to 1.5 lb/sq ft and of coefficients of rigidity from 1/2 to 2 centipoise. Two different cases were studied: a heat exchanger having fixed axial and radial delta T in which the tube length was allowed to vary and a heat exchang… more
Date: June 10, 1957
Creator: Thomas, D. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Observed performance of the Fuel Sample Cooler

Description: Measurements of flow rate through the fuel high-pressure system sampler indicate that the average flow rates is about 0.29 gpm (145 lb/hr) plus or minus 50%, which affords an adequate purge of from 12 to 36 volumes through the sample line if the full fifteen minutes of purging is allowed before isolating the sample. The fuel sample cooler was fund to have adequate capacity to reduce the temperature of the fuel solution form about 275 to 70 C, using pre-heated cooling water at 70 C. Uncertaintie… more
Date: June 3, 1957
Creator: Van Winkle, R. & Wiethaup, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Observed Net Heat Loss from the HRT High-Pressure System

Description: An estimate has been obtained of the heat that should be generated in the HRT core in order to hold the system at operating temperature under no-load conditions. This estimate was made by measuring the feed-water rate to the package boiler during an oxygenated water rung. Results are summarized.
Date: June 4, 1957
Creator: Van Winkle, R. & Wiethaup, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Disposal of Power Reactor Waste Into Deep Wells

Description: For various reasons it is not possible to leave the uranium or other nuclear fuel in a power reactor until all of it has been "burned up" by fission. In the case of liquid fuel (homogeneous) reactors a small part is continuously bled out, purified and returned. In the case of solid fuel reactors, fuel elements are periodically removed, reprocessed and the "unburned" fuel put back into service. In both cases the purification produces wastes which contain radioactive fission products and transura… more
Date: June 13, 1957
Creator: De Laguna, Wallace, 1910- & Blomeke, J. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRT Letdown Valves

Description: To supply information about the several letdown valves which have been in HRT service, a typical valve plug examined by the Metallurgy Section confirms the belief that chemical attack on the Stellite #6 was occurring. It appears that most of the corrosion was due to rinse solutions, since this phenomenon has not been noted on letdown valves in the HRT Mockup where over 90% of the operating time has been with UO2SO4 solutions.
Date: June 5, 1957
Creator: Billings, A. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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September, 1956, Measure of Radiation level of HRE Fuel System Components (After Storage for 27 Months)

Description: Radiation level measurements of various HRE fuel system components, made in September, 1956, after 27 moths of storage, are compared with the June, 1954, readings before storage. Measurements were made with a standard cutie pie and results tabulated.
Date: June 5, 1957
Creator: Haynes, T. E. & Van Winkle, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Cleaning and Storage of the HRT Steam and Closed Cooling Water Systems

Description: A 10% phosphoric acid solution contain 0.2% "Rodine 45" inhibitor is recommended to be used for the chemical cleaning of the HRT seam and closed colling water systems. Wet storage is recommended for both of these systems. The steam system is to be stored with steam condensate containing 100 ppm hydrazine, and closed cooling water system is to be stored with steam condensate containing 1000 ppm potassium chromate.
Date: June 5, 1957
Creator: McLain, Howard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Reaction of Zirconium with Uranium Dioxide

Description: An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date: June 11, 1957
Creator: Robinson, M. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRP In-Pile Corrosion Test Loops -- Operation of In-Pile Loop L-2-10

Description: Loop L-2-10 was the eighth completed in-pile loop experiment and the first in the HB-2 beam hole at the LITR. The loop was inserted on July 2, 1956 and removed on September 3, 1956. The installation, operation, removal, and general performance of the HRP in-pile solution corrosion loop in the HB-2 beam hole at the LITR are described.
Date: June 13, 1957
Creator: Walter, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of Corrosion Data for HRT Mockup Operational Period Ending February 16, 1957

Description: The HRT mockup was shut down February 16, 1957 after operating for 576 hours on high concentration uranyl sulfate. At this time, all corrosion samples in the system were removed and replaced, and the wire extending thought the letdown hear exchanger was removed of examination.
Date: June 17, 1957
Creator: Wacker, R. E. & Griese, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Liquid-Liquid Extraction of Uranium and Plutonium from Hydrochloric Acid Solution with TRI (Iso-Octyl) Amine. Separation of Uranium and Plutonium from Thorium and Fission Products

Description: A new and rapid method for the liquid-liquid extraction of uranium and plutonium from hydrochloric acid solution is based on the use of tri(iso-octyl)amine dissolved in xylene or methylisobutylketone. Uranium and/or plutonium are separated from thorium, alkalis, alkaline earths, rare earths, zirconium, niobium, ruthenium and other elements which do not form anionic species under the conditions described. The technique may be used for either tracer or macro quantities of uranium. Several practic… more
Date: June 18, 1957
Creator: Moore, Fletcher L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spectrophotometric Determination of Cerium with Tiron

Description: A spectrophotometric method for the determination of cerium with Tiron (disodium-1,2-dihydroxybenzene-3,5disulfonate) was applied to the determination of cerium in samples which contain uranium and zirconium. The cerium-Tiron complex in solutions of pH 8 or greater exhibits an absorption maximum of 500 mu . This reagent does not react with any other lanthanide element. The interference of iron, uranium, and zirconium was eliminated by extracting these interfering elements with a solution of tri… more
Date: June 14, 1957
Creator: McDowell, B. L.; Meyer, A. S., Jr. & White, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Test Results on a Heater-Cooler Unit for the ORR In-Pile Loop

Description: Tests have been completed on a combination heater-cooler unit for use in in-pile loops designed to operate in beam hole HN-1 of the ORR facility. The unit is designed to use air-water mixtures as the coolant. the coolant flows through a spiral of 3/8-inc. diameter tubing cast in aluminum around the 3/8-in. IPS loop pipe. four 1000-w calrod-type electric heating elements are cast into the aluminum, along with the cooling coils to provide loop heating.
Date: June 28, 1957
Creator: Mauney, T. H. & Savage, H. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Loop Components and Admixed Thorium-3% Uranium Oxide Slurry in 200A Loop (Summary of Run 200A-10)

Description: A slurry addition system, a venturi in the circulation loop, and two types of sampling systems were tested with 500 and 800 g Th/kg H2O slurries in the 200 gpm loop at 250 C and 1000 psig. The addition system worked satisfactorily while the venturi gave erratic readings during part of the run. Both the capillary and in-line sampling systems proved satisfactory with the capillary sampler being much easier and more convenient to operate. The addition of uranium to the slurry had no appreciable ef… more
Date: June 13, 1957
Creator: Gallaher, R. B.; Kitzes, A. S. & VandenBulck, C. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dynamic Corrosion Screening Tests on Inconel and Nickel in NaCl-MgCl2-UCl3 Bath

Description: Nickel is more susceptible to mass transfer in a 100hr non-isothermal dynamic corrosion system than is Inconel when exposed to a NaCl-MgCl2-UCl3 (50.0-33.3-16.0 mole %) bath at a hot zone temperature 1800 F. No nickel mass transfer was observed in a 500-hr test at 1350 F, but Inconel showed some attack under these conditions. Inconel mass transfer was observed in both tests, being more severe at the higher temperature. On the bases of these preliminary tests, it appears that nickel is a more… more
Date: June 19, 1957
Creator: Jansen, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Trip to Selas Corporation of America

Description: On May 23, 1957, a visit was made by the writer to the Selas Corporation of American in Dresher, Pennsylvania. The purpose of the visit was to discuss further investigations into methods of tubesheet brazing by direct heating. Original work along these lines has been carried out at ORNL and is covered by a memo (CF-57-4-57) to W.D. Manly, dated April 16, 1957, and entitled : Investigation of Tubesheet Brazing by a Method of Direct Heating.
Date: June 18, 1957
Creator: Franco-Ferreira, E. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Trace Amounts of Sulfur in Fluoride Salts

Description: A method has been developed for the determination of total sulfur in fluoride salts using the methylene blue procedure. Reduction of sulfate to hydrogen sulfide is achieved through the use of a new reducing mixture consisting of stannous chloride dissolved in concentrated phosphoric acid. The new mixture is effective on microgram amounts of sulfate and offers a major advantage over the red phosphorous reducing mixtures in that larger samples may be taken for analysis. The procedure has been app… more
Date: June 24, 1957
Creator: Gilbert, T. W. & White, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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