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DISSOLUTION OF BeO-AND Al$sub 2$O$sub 3$-BASE REACTOR FUEL ELEMENTS. PART I

Description: Aqueous methods for recovering uranium from BeO- and Al/sub 2/O/sub 3/- base gas-cooled-reactor fuel elements are being evaluated. Two methods for processing Hastelloy-X--clad pelletized BeO-base fuels containing 60 to 70% UO/ sub 2/, such as the GCRE and MGCR, seem feasible. One method involves mechanical stripping or chopping of the cladding followed by leaching of the uranium from the fuel pellets with boiling 6-l3M HNO/sub 3/. In the other method the cladding and UO/sub 2/ are dissolved in … more
Date: February 14, 1962
Creator: Warren, K S; Ferris, L M & Kibbey, A H
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Phase Transformations in Alumina. Technical Report, May to December 1961

Description: e transformation studies showed that synthetic aluminas produced in the laboratory were not transformed to alpha alumina at 400 to 700' deg n the presence of nitric acid and water vapor. Amorphous aluminn produced in the pilot plant was transformed to alpha alumina. This indicated that the amorphous alumina produced in the pilot plant is structurally predisposed to form alpha alumina. Most additives did not appear to have any special effects. Lithium formed zeta alumina, LiAl/sub 5/O/sub 8/. Ph… more
Date: December 1, 1961
Creator: Eding, H J; Huggins, M L & Brown, A G
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Secondary recovery of plutonium and americium from process waste streams by solvent extraction

Description: A solvent extraction process is being evaluated for the secondary recovery of plutonium and americium from Rocky Flats waste streams. The bidentate organophosphorus compounds dihexyl-N,N-diethylcarbamylmethylene phosphonate and its dibutyl analogue have been shown to be selective extractants for the actinides from solutions of nitric acid. The results from laboratory test runs in which the organophosphorus extractants were used for processing secondary waste solutions will be presented. Solvent… more
Date: January 16, 1978
Creator: Hagan, P. G. & Navratil, J. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report, April 1962

Description: Bubble size measurements in the foam column showed that a spinnerette with 50 mu holes gave a nearly normal distribution of bubbles sizes while a coarse fritted glass gas sparger had a tail of large bubbles which did not fit the normal curve. A set of equations solvable by a finite difference technique are presented which completely describe the irreversible reaction rate of H/sub 2/ or CO with a fixed bed of CuO pellets. Radiation damage tests are in progress to evaluate plastics for the Trans… more
Date: October 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preparation of Uranium(IV) Nitrate Solutions

Description: A procedure was developed for the preparation of uranium(IV) nitrate solutions in dilute nitric acid. Zinc metal was used as a reducing agent for uranium(VI) in dilute sulfuric acid. The uranium(IV) was precipitated as the hydrated oxide and dissolved in nitric acid. Uranium(IV) nitrate solutions were prepared at a maximum concentration of 100 g/l. The uranium(VI) content was less than 2% of the uranium(IV). (auth)
Date: July 1, 1961
Creator: Ondrejcin, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, October-December 1961

Description: The ICPP processed Al fuel, prtncipally of the MTR-ETR type, durtng this quarter. Newly designed and installed processing equipment exhibited excellent operating performance. This included direct-air-pulsed extraction, stripping and scrub columns, and a cascade-controlled continuous evaporator in first cycle product concentration service. Aqueous zirconium fuel processing studies continued with the objective of adapting the hydrofluoric acid process to continuous dissolution-complexing to incre… more
Date: March 28, 1962
Creator: Bower, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHEMICAL PROCESSING OF COATED PARTICLE FUELS

Description: BS>Laboratory studies on the processing of graphite-base fuel elements containing pyrolytic carbon- or Al/sub 2/O/sub 3/-coated particles are reviewed. Potential processes for recovering U and Th from irradiated elements include grinding followed by acid leaching, and, burning and subsequent dissolution of the oxide ash. Disintegration in 90% HNO/sub 3/ was briefly evaluated as a method for determining the integrity of coated particles dispersed in graphite matrices. (auth)
Date: April 1, 1962
Creator: Ferris, L.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of plutonium from HEPA filters by Ce(IV): promoted dissolution of PuO/sub 2/ and recycle of the cerium promoter

Description: Studies carried out in this investigation included (1) electrolytic production of Ce(IV) from Ce(III), (2) leaching of refractory PuO/sub 2/ from HEPA filters with maintenance of Ce(IV) by anodic oxidation during leaching, and (3) evaluation of methods for contacting the HEPA solids with the leaching solution and for separating the solid residue from the leaching liquor. Anodic oxidation of Ce(III) was accomplished with an electric current efficiency of about 85% at current densities of 0.04 to… more
Date: May 1, 1980
Creator: Scheitlin, F.M. & Bond, W.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report, November 1961

Description: Openation of a 6-in.-dia foam separation column with Sr/sup 89/ tracer and dodecylbenzenesulfonate as a surfactant and foaming agent was continued. The catalytic oxidation of H/sub 2/, CO, and CH/sub 4/ was studied using a nickel- chromepalladium ribbon catalyst. A Mark I prototype fuel assembly was sheared to within 1.5-in. of the end by modifying the gas hydraulic system of the shear. The force required to shear a highly carburized Mark I fuel assembly ductile tubing. Demonstration of the mec… more
Date: May 16, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Simultaneous analysis of uranium and nitrate

Description: A direct spectrophotometric method has been developed for the determination of 20 to 200 g/l of uranium in the presence of 3 to 5 M nitric acid. A dual-wavelength analysis is used to eliminate the enhancing effect of nitrate ion on the uranium visible spectra. The precision and accuracy of the simultaneous analysis of uranium and nitrate were compared using combinations of the four uranium wavelength maxima, occurring at 426, 416, 403 and 359 nm. Calculations based on 426 and 416 nm data yielde… more
Date: April 1, 1978
Creator: Bostick, D.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Procedure for the analysis of americium in complex matrices

Description: A radioanalytical procedure for the analysis of americium in complex matrices has been developed. Clean separations of americium can be obtained from up to 100 g of sample ash, regardless of the starting material. The ability to analyze large masses of material provides the increased sensitivity necessary to detect americium in many environmental samples. The procedure adequately decontaminates from rare earth elements and natural radioactive nuclides that interfere with the alpha spectrometric… more
Date: February 1, 1978
Creator: Knab, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ceramic and cermet targets

Description: Use of isotopic materials as targets in high temperature environments, e.g., reactor cores, require that chemically stable forms of the isotopes be employed. Usually oxides are compatible with temperatures > 1600/sup 0/K, although some light element oxides exhibit some volatility at temperatures > 1300/sup 0/K. Especially in the case of heavy elements, the relatively low melting points of the metals, poor compatibility of the metals with encapsulation materials, and high chemical reactivity at … more
Date: January 1, 1979
Creator: Kobisk, E. H.; Quinby, T. C. & Aaron, W. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Double liquid membrane system for the removal of actinides and lanthanides from acidic nuclear wastes

Description: Supported liquid membranes (SLM), consisting of an organic solution of n-octyl-(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) and tributyl-phosphate (TBP) in decalin are able to perform selective separation and concentration of actinide and lanthanide ions from aqueous nitrate feed solutions and synthetic nuclear wastes. In the membrane process a possible strip solution is a mixture of formic acid and hydroxylammonium formate (HAF). The effectiveness of this strip solution is redu… more
Date: January 1, 1985
Creator: Chiarizia, R. & Danesi, P.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparative Evaluation of DHDECMP (dihexyl-N,N-diethylcarbamoyl-methylphosphonate) and CMPO (octylphenyl-N,N,-diisobutylcarbamoylmethylphosphine oxide) as Extractants For Recovering Actinides From Nitric Acid Waste Streams

Description: Certain neutral, bifunctional organophosphorous compounds are of special value to the nuclear industry. Dihexyl-N,N-diethylcarbomoylmethylphosphonate (DHDECMP) and octylphenyl-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) are highly selective extractants for removing actinide and lanthanide elements from nitric acid. We obtained these two extractants from newly available commercial sources and evaluated them for recovering Am(III), Pu(IV), and U(VI) from nitric acid waste streams of pluto… more
Date: February 1, 1988
Creator: Marsh, S.Fredric & Yarbro, Stephen L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium(IV) hydrous polymer chemistry

Description: The hydrous polymer chemistry of Pu(IV) in aqueous nitric acid solutions has been a subject of considerable interest for several years. This interest stems mainly from the fact that most nuclear fuel reprocessing schemes based on the Purex process can be hampered by the occurrence of polymer. As a result, an understanding and control of the parameters that affect polymer formation during reprocessing are studied. 2 refs.
Date: January 1, 1985
Creator: Toth, L.M. & Dodson, K.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A Modified Pyroelectric Sodium Fluoride Carrier Distillation Medthod For The Spectrographic Analysis Of Impurities In Plutonium

Description: A modification of the pyroelectric sodium fluoride carrier distillation method for analysis of impurities in plutonium metal is described. The metal is dissolved. Plutonium is precipitated and treated with nitric acid. The slurry obtained is dried and ignited. The resultant low density oxide is mixed with sodium fluoride and pressed into a pellet for arcing. Cobalt is used as the internal standard for densitometric using visual comparisons against prepared standards. The procedural modification… more
Date: August 1, 1966
Creator: Schreiber, G. A. & Barrick, C. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 1

Description: Four runs were conducted in the Zirflex-Sulfex headend hot cell equipment. Prototype PWR blanket rods, Zircaloy2 clad UO/sub 2/, irradiated from 159 to 356 Mwd/t and decayed 2 years, were declad in boiling 6 M NH/sub 4/F-l M NH/sub 4/NO/sub 3/, terminating with a F/Zr mol ratio of 7 in the spent decladding solution. Average decladding time was 1.5 hr, leaving end cap residues of about 5 g per pin. At the end of the decladding, maximum loss of uranium and plutonium to the decladding solution was… more
Date: January 11, 1962
Creator: Goode, J.H. & Baillie, M.G.
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 1962

Description: The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissol… more
Date: June 29, 1962
Creator: Bower, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Investigation of the Corrosion Resistance of Brazing Alloys for Austenitic Stainless Steel Fuel Elements for Service in 565 F Pressurized Water

Description: Since brazing was the method selected for joining the stainless steel SM- l reactor fuel element, corrosion studies were conducted on various potential brazing alloys to evaluate their resistance under the approximate pressurized- water conditions of the SM-1. The program consisted mainly of testing type 304L stainless steel T'' joints brazed with selected alloys in quiescent, degassed, and deionized autoclaved water at 565 deg F under 1200-psi pressure. In the initial phase of the investigatio… more
Date: April 12, 1962
Creator: Beaver, R. J.; Leitten, C. F. Jr. & English, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Bench-Scale Natural-Recirculation Dissolver

Description: A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated M… more
Date: January 10, 1962
Creator: Erickson, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Method for cleaning solution used in nuclear-fuel reprocessing.

Description: A nuclear fuel processing solution containing: (1) hydrocarbon diluent; (2) tri-n-butyl phosphate or tri-2-ethylhexyl phosphate; and (3) monobutyl phosphate, dibutyl phosphate, mono-2-ethylhexyl phosphate, di-2-ethylhexyl phosphate, or a complex formed by plutonium, uranium, or a fission product thereof with monobutyl phosphate, dibutyl phosphate, mono-2-ethylhexyl phosphate, or di-2-ethylhexyl phosphate is contacted with silica gel having alkali ions absorbed thereon to remove any degradation … more
Date: May 12, 1981
Creator: Tallent, O. K.; Dodson, K. E. & Mailen, J. C.
Item Type: Refine your search to only Patent
Partner: UNT Libraries Government Documents Department
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Corrosion of high Ni-Cr alloys and Type 304L stainless steel in HNO/sub 3/-HF

Description: Nineteen alloys were evaluated as possible materials of construction for steam heating coils, the dissolver vessel, and the off-gas system of proposed facilities to process thorium and uranium fuels. Commercially available alloys were found that are satisfactory for all applications. With thorium fuel, which requires HNO/sub 3/-HF for dissolution, the best alloy for service at 130/sup 0/C when complexing agents for fluoride are used is Inconel 690; with no complexing agents at 130/sup 0/C, Inco… more
Date: April 1, 1980
Creator: Ondrejcin, R.S. & McLaughlin, B.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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