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in publisher: "Phillips Petroleum Company. Atomic Energy Division."  
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Removal of Radioisotopes From Solution by Earth Materials From Eastern Idaho

Description: Abstract: Naturally occurring earth materials from Idaho, primarily from localities near the National Reactor Testing Station (NRTS), were used in laboratory tests for the removal of radioisotopes from aqueous solutions. These earth materials included lignitic deposits, clay-like materials, and specific minerals; ion exchange resins were also considered for a specific application. The aqueous solutions were low-level radioactive cooling water or synthetic solutions made up to represent low-lev… more
Date: April 1964
Creator: Wilding, M. W. & Rhodes, D. W. (Donald Walter), 1919-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low Temperature Polymorphic Transformations of Calcined Alumina

Description: The factors which affect the transformation of amorphous alumina to crystalline alumina in the temperature range 350 to 650/sup 0/C were studied. Amorphous alumina, with small amounts of added impurities, was heated in an atmosphere containing the oxides of nitrogen, air, and water vapor, and the amount of crystalline alumina was determined. Alpha alumina was the predominant crystalline form after heating amorphous alumina that was prepared in a fluid bed calciner. The effects of temperature, c… more
Date: September 28, 1962
Creator: Murray, R. F. & Rhodes, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Pilot Plant Calciner. Part I. Equipment Development and Initial Process Studies

Description: A two-foot-square fluidized bed calciner was designed and operated to convert aqueous, highly radioactive wastes into granular solids. The calciner exceeded its designed feed capacity of calcining, at a bed temperature of 400/sup 0/C, 100 liters per hour of aluminum nitrate solution simulating wastes from the reprocessing of spent aluminum-uranium alloy reactor fuel. Heat was supplied to the calciner by circulating NaK with an electromagnetic pump, at temperatures up to 1400/sup 0/F, through a … more
Date: June 20, 1962
Creator: Brown, B. P.; Grimmett, E. S. & Buckham, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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STAINLESS STEEL WASTES. III. LABORATORY STUDIES OF THE RATE OF REMOVAL OF STAINLESS STEEL IONS BY MERCURY CATHODE ELECTROLYSIS

Description: ABS> The removal rates of iron, nickel, and chromium from synthetic stainless steel waste solutions during electrolysis over a mercury cathode were studied. The loading capacity of the mercury for the stainless steel metals was estimated on the basis of laboratory experiments to be about two% by weight. The laboratory data indicated that, at an electrode potential of --1.80 voits vs S.C.E., 85 ampere-hours per liter of waste removed essentially all of the stainless steel ions from a sulfuric ac… more
Date: February 12, 1962
Creator: Anderson, D. R. & Rhodes, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mixing and Evaporation in a Packed Vessel

Description: In connection with an evaluation of the operability of a 36-inch diameter remote evaporator at the Idaho Chemical Processing Plant that was to be packed with a corrosionresistant neutron-poison packing for criticality control, an investigation in a 30-inch diameter vessel proved that air sparging effectively mixes solutions. The data showed that at similar spar;e rates the presence of the packing caused an increase in the time needed for complete mixing. The investigation showed that solutions … more
Date: September 20, 1961
Creator: Cederberg, C. K. & Buckham, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Heavy Water Purity by Infrared Absorption

Description: The practical application of heavy water purity determination by infrared absorption spectroscopy using standard laboratory equipment was demonstrated in connection with the operation of heavy water-moderated Special Power Excursion Reactor Test (SPERT II) Facillty at the NRTS. (auth)
Date: January 16, 1962
Creator: Abernathey, R. M. & Morgan, T. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium Fluozirconate Precipitation Process for Zirconium Fuels. Part 1. Laboratory Development

Description: Precipitation, evaporation, and extraction feed preparation conditions are established for the removal of zirconium and fluoride from fuel dissolver product solutions by the addition of sodium formate. A sparingly soluble complex fluozirconate is formed. Ninety-five to 99% of the zirconium and fluoride is separated from the uranium losses of 0.1% or less. Chemical material balances, based on experimental data, were developed for two flowsheets. In one flowsheet, sufficient nitric acid is added … more
Date: May 15, 1962
Creator: Newby, B. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SPERT IV HAZARDS SUMMARY REPORT

Description: Spert IV is a large pool-type experimental facility for reactor kinetic studies. These studies will include power excursion and instability tests for a variety of reactor designs. Since the Spert IV experimental program requires the performance of tests which will approach, and may exceed the threshold of reactor destruction, the probability of occurrence of the maximum possible accident is not negligible compared with that of other possible accidents. The maximum possible accident for this fac… more
Date: July 1, 1961
Creator: Bentzen, F. L. & Crocker, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proceedings of the 1960 Idaho Conference on Reactor Kinetics Held at Sun Valley, Idaho, October 12-14, 1960

Description: >Thirty papers are included on reactor kinetics with emphasis being placed on reactor safety and design considerations resulting from kinetic work. Information is presented on power excursion programs, reactor transfer function determination and application, reactor instability and thermal-hydraulic problems, and analytical methods in reactor kinetics. The accomplishments in the field and areas needing emphasis are discussed and summarized. Constructive suggestions are made on program direction… more
Date: July 1, 1962
Creator: Haire, J. C. & Bright, G. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SALT PHASE CHLORINATION OF REACTOR FUELS. IV. NIOBIUM BEHAVIOR IN THE LEAD CHLORIDE AND CHLORINE-LEAD CHLORIDE SYSTEMS

Description: Investigation of the behavior of Nb in PbCl/sub 2/ showed that the Nb dissolution rate is quite low. Since stirring increases the rate appreciably, it is likely that the initial reaction is diffusion controlled. A subsequent reaction is linear in rate with an activation energy of 23.4 kcal per mole. Incomplete volatilization of dissolved Nb from PbCl/sub 2/ is due to the presence of lower oxidation states of Nb. The addition of Cl to PbCl/sub 2/ increases the rate of dissolution of Nb. The rate… more
Date: March 15, 1962
Creator: Teague, J. L.; Hahn, H. T. & Vander Wall, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation and Measurement of the Transient Temperature in a Low- Enrichment UO$sub 2$ Fuel Rod During Large Power Excursions

Description: The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element are presented. The tests were performed to investigate the possibility of damage to such long thermal-time-constant fuel rods when subjected to short-period power excursions, and to test the effectiveness of an instrumentation technique for measurement of UO/sub 2/ fuel temperatures within the rods. In an initial series of power excursion tests, in which the range of reactor periods was from appr… more
Date: May 18, 1962
Creator: Houghtaling, J. E.; Quigley, T. M. & Spano, A. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Propane Vibrational Analysis

Description: Using the group vibratibn method of McMurry, the normal frequencies and coordinates of propane and three of its symmetrical deuterium substituted compounds were obtained. The force constants used were taken from a variety of previous works on hydrocarbons. The results give reasonable agreements with the experimental frequency and mode assignments of others. (auth)
Date: June 12, 1962
Creator: Marshall, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim Report on the Development of an Air Pulser for Pulse Column Application

Description: The Idaho Chemical Processing Plant for several years has been studying various pulsing systems, used in extraction columns for processing irradiated nucIear fuel elements, in an effort to eliminate the mechanical difficuittes in present pulsing systems. An air puising system has been demonstrated, and a discussion is given of experimental work, pulser design, and plant operational experience with this system. It is concluded, from work completed thus far that air puising of extraction columns … more
Date: September 22, 1961
Creator: Weech, M. E.; P'Pool, R. S. & MacQueen, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, January-March 1961

Description: Studies are reported on aqueous zirconium processing, dissolution of BeO- UO/sub 2/ ceramic fuel, the aqueous stainless steel process, the behavior of dibutyl phosphates, use of boron (boric acid) solution to assure critical safety, fluidized bed calcination, conversion of amorphous alumina to alpha alumina, the Demonstrational Waste Calcining Facility, removal of long-lived radioisotopes from waste solutions, separation of iron, nickel, and chromiun from stainless steel waste solutions, electr… more
Date: October 31, 1962
Creator: Bower, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REMOTE DISSOLUTION AND ANALYTICAL PROGRAM FOR IRRADIATED THORIUM

Description: A remote dissolution and analytical program for irradiated thorium is given. The aluminum jacket on the slug was dissolved with 6M nitric acid and 0.005M mercuric nitrate. After a water wash, the thorium dissolution was accomplished with concentrated nitric acid made 0.04M in hydrofluoric acid. Weighing, dissolving, and sampling were done remotely in the multicurie cell at the Idaho Chemical Processing Plant. Handling techniques for weighing and dissolving the slugs are described. Transferring … more
Date: July 14, 1961
Creator: Huff, G. A.; Doggett, I. L.; Fletcher, R. D. & Jacobson, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SALT PHASE CHLORINATION OF REACTOR FUELS. III. CATALYZED DISSOLUTION OF URANIUM DIOXIDE IN LEAD CHLORIDE-CHLORIDE SYSTEMS

Description: The rapid dissolution of uranium dioxide is described, wherein copper is added to molten lead chloride at 550 deg C. and chlorine is passed through the melt. The integral dissolution of zirconium-clad uranium dioxide fuels is also described. The dissolution rate of uranium dioxide is directly proportional to the concentration of cuprous chloride if an excess of chlorine is used; the value for the rate constant is approximately 100 mg (UO/sub 2/) cm/sup -2/ min/sup -1/ (CuCl molality). The urani… more
Date: February 1, 1962
Creator: Vander Wall, E. M.; Bauer, D. L. & Hahn, H. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Method of Determining the Intermediate Energy Neutron Dose

Description: The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediat… more
Date: March 10, 1961
Creator: Hankins, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Improved Sample Bonding and Emission With Tantalum Surface Ionization Filaments

Description: Techniques for conditioning of Ta filaments for improved bonding and emission with a Ta metal powder-Ta/sub 2/O/sub 5/ mixture are described. A porous Ta metal layer is deposited which restricts sample to the filament. Metal- oxide ion emission is enhanced with additional Ta/sub 2/O/sub 5/ to the porous layer. Reduction of fractionation through action of liquid Ta/sub 2/O/sub 5/ is discussed in particular for Sr+ emission. Use of conditioned filaments for rapid U concentration analysis with a s… more
Date: June 29, 1962
Creator: Goris, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Tests in Molten Lead-Lead Chloride

Description: Corrosion tests were run on some commercial grade metals, an alloy steel, stainless steels, chromium-- nickel-iron alloys, nickel base alloys, cobalt base alloys, and a chromium-- nickel-- cobalt-- iron ailoy in the system: leadlead chloride-lead chloride vapor at 528 deg C under an argon atmosphere. The following metals and alloys showed a corrosion rate of nine mils per month or less and did not suffer intergranular or other localized attack: tantalum, Incoloy 804, Hastelloy F, Carpenter-20 (… more
Date: June 1, 1961
Creator: Stolica, N. D.; Adams, G. S. & Bomar, M. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART I. ZIRCONIUM IN HCl- METHANOL

Description: The electrolytic dissolution of zirconium in HCl-methanol was studied as a function of potential, solution composition, and temperature. The dissolution is characterized by two regions. At high potentials the zirconium is electropolished and complete dissolution is achieved. At low potentials the current is an exponential function of the potential (Tafel behavior). In this region a small amount of finely divided alpha -zirconium which is insoluble in HCl-methanol separates from the bulk metal. … more
Date: December 29, 1961
Creator: Aylward, J. R.; Whitener, E. M. & Hahn, H. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina

Description: A seven- to twenty-fold volume reduction can be obtained from fluidized bed calcination of aqueous aluminum nitrate wastes, depending on the operating conditions employed and their effect on the intra-panticle porosity and absolute density of the calcined alumina. Among the calcining variables, only the bed temperature and the fuel aluminum concentration had a significant effect on the intra-particle porosity of alumina generated during studies conducted primarily in a two-foot-square fluidized… more
Date: July 25, 1962
Creator: Wheeler, B. R.; Grimmett, E. S. & Buckham, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MTR Fast Neutron Flux Measurements for Cycle 146

Description: The fast neutron fluxes in selected positions of the MTR were measured for Cycle 146. The measurements were made at the beginning, throughout, and at the end of the cycle (564 Mwd). Vertical traverses for each position monitors are shown. (auth)
Date: March 20, 1962
Creator: Weber, L. D. & Hogg, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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