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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961

Description: Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacke… more
Date: April 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, May 1961

Description: The experimental results on the oxidation of H from a He stream with CuO pellets were very close to the predicted behavior based on the mathematical model. Experimental measurements of uranyl sulfate loading rates on chloride equilibrated resin showed little variation with solution concentrations. A tentative flowsbeet was proposed for cost analysis of processing a Pebble Bed Reactor. A U-Zr plate was dissolved in nitrate-free Zirflex solution. An authentic TRIGA prototype was processed in engi… more
Date: December 26, 1961
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Use Test Comparison of TBP Diluents

Description: Several diluents for possible use in TBP Purex Plant solvent were tested. The tests included nitric --nitrous acid degradation, fission prcduct distribution under simulated plant conditions, emulsillcation, and radiolysis. The order of quality of four diluents is n-dcdecane> Soltrol 170> Shell Code 85030(82000)> Shell E-2342. (D.L.C.)
Date: July 1, 1961
Creator: Mendel, J. E.
Partner: UNT Libraries Government Documents Department
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Rockwell Hanford Operations' 1978 radiological improvement program

Description: This document describes the radiological improvement program (RIP) to be undertaken by Rockwell Hanford Operations during calendar year 1978. Actions taken in each facility to reduce exposure and to implement the Company's policy to conduct operations in a manner that assures radiation exposures to employees are maintained at the lowest levels reasonably achievable.
Date: December 30, 1977
Creator: Cunningham, D. S.
Partner: UNT Libraries Government Documents Department
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THE EFFECTS OF INTERNAL HEAT GENERATION ON POT CALCINATION RATES FOR RADIOACTIVE WASTES

Description: Methods by which the radial deposition mechanism was determined in experiments with simulated waste solutions are reviewed. Based on this mechanism, an expression for the rate of solid deposition with internal heat generation was developed by a combined heat and material balance. A sample calculation for Purex waste showed that a moderate heat generation rate of 5000 Btu/hr/ft/sup 3/ would decrease the time to fill a 12-in.-dia calcination vessel from 78 to 55 hr. For the calcination stage of t… more
Date: October 23, 1961
Creator: Perona, J.J.
Partner: UNT Libraries Government Documents Department
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Evaluation of Hydrocarbon Diluents for the Purex Process

Description: Forty-nine hydrocarbon products were evaluated in the laboratory in a search for a highly stable diluent for the organic extractant used in a radiochemical separations plant. The formation of zirconium ligands during chemical and radiolytic degradation increased with boiling point for isoparaffinic producte but was approximately constant for n-parafiins. Of those materials that met the local flash point specification, the n-parafiins were superior. (auth)
Date: November 1, 1961
Creator: Dennis, B. P. & West, D. L.
Partner: UNT Libraries Government Documents Department
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Potential of pyroprocessing for partitioning purex wastes

Description: The processes are extremely compact. The process reagents are highly resistant to radiation damage and, therefore, can be used to handle short-cooled, highly concentrated waste with negligible degradation. Most reagents can be recycled back through the process many times, thereby minimizing the generation of waste products, and also reducing the process cost. Fission-product wastes are discharged from the process as concentrated, solid wastes, typically in a metal matrix suitable for permanent … more
Date: July 23, 1980
Creator: Coops, M. S. & Sisson, D. H.
Partner: UNT Libraries Government Documents Department
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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3

Description: ABS>Hot cell demonstration of the Zirflex decladding process coupled with a modified Purex solvent extraction process was completed using specimens of Zircaloy-clad UO/sub 2/ irradiated to levels of 6150-14,600 Mwd/TU. Soluble losses of uranium and plutonium to the decladding solutions were about 0.05%. Centrifugation of the decladding solution is probably necessary to remove up to 1% of the UO/sub 2/ present as fines resulting from the fracture of low (93 to 95%) density pellets; high (96%) de… more
Date: May 14, 1962
Creator: Goode, J.H. & Baillie, M.G.
Partner: UNT Libraries Government Documents Department
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LABORATORY PROGRESS ON THE DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE BY DEEP- WELL INJECTION

Description: Results of laboratory studies on the neutralization of Purex-type wastes are reported, including the radiochemical distribution of the fission products in the precipitate and supernate and the effect of sodium and calcium neutralizations on fission-produet separation. The problem of interstitial precipitation encountered when a second incompatible liquid is injected into a formation is discussed. Results indicate a piston-iike displacement of the interstitial liquid by the injected waste with o… more
Date: March 1, 1962
Creator: Lacy, W.J.; Sealand, O.M.; Jacobs, D.G. & Struxness, E.G.
Partner: UNT Libraries Government Documents Department
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Actinide partitioning and transmutation program. Progress report, July 1--September 30, 1977

Description: In Purex process modifications, two cold runs with mixer-settlers were made on the extraction and stripping of ruthenium and zirconium without the presence of uranium. Efforts in actinide recovery from solids were directed toward the determination of dissolution parameters in various reagents for /sup 241/Am and /sup 239/Pu oxide mixtures, /sup 233/U oxide, /sup 237/Np oxide, /sup 244/Cm oxide, /sup 232/Th oxide, and PuO/sub 2/. Studies in americium-curium recovery with OPIX (oxalate precipitat… more
Date: February 1, 1978
Creator: Tedder, D.W. & Blomeke, J.O. (comps.)
Partner: UNT Libraries Government Documents Department
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LABORATORY DEVELOPMENT OF A CARRIER-PRECIPITATION PROCESS FOR THE RECOVERY OF STRONTIUM FROM PUREX WASTES

Description: Strontium recovery from Purex 1WW was investigated with simulated feeds and tracer activities. Initial experiments demonstrated recovery of over 70% of the strontium by sulfate precipitation from partially neutralized 1WW by either increasing the sulfate concentration to about 3 M or by adding carriers such as lead. Precipitation of iron was avoided by addition of one or more moles of tartrate per two moles of iron. Precipitation at elevated temperatures and addition of lead after pH adjustment… more
Date: May 1, 1961
Creator: Bray, L.A. & Van Tuyl, H.H.
Partner: UNT Libraries Government Documents Department
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The Fluid-Bed Calculation of Radioactive Waste

Description: Liquid radioactive wastes are converted into solids, with volume reduction factors of 3 to 8, by flash drying on finely screened, porous, inert solid particles (e.g. alumina) in a fluidized bed at 320 to 550 deg C. The wastes may be either aluminum nitrate-containing wastes from the processing of MTR-type fuel elements, or Purex Process wastes. Ruthenium is found to be the only volatile fission product in this temperature range. Methods are described for its removal from the fluidizing gas. (T.… more
Date: May 1, 1961
Creator: Loeding, J. W.; Carls, E. L.; Anastasia, L. J. & Jonke, A. A.
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.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, August 1961

Description: Engineering studies of a 6-in.-ID countercurrent foam column were started. The capacity of Mark II Stacked Clone Contactor was found to be limited by gradually increasing entrainment. Thoria sols were prepared from trough denitrator products in a conical bottom tank agitated by circulation through an external centrifugal pump. Experimental results agreed favorably with predicted results for the reaction of CO with CuO and fur the simultaneous reactions of H/ sub 2/ and CO with CuO. In a 2-in. d… more
Date: March 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Alternate fuel cycle technologies. Quarterly report, April--June 1977

Description: This quarterly report describes studies to provide information needed to close the back end of the commercial light-water reactor (LWR) fuel cycle. These efforts are directed primarily at reprocessing and recycle of uranium and plutonium from spent LWR fuel. Research is reported in the following categories: environmental studies, fuel receipt, head-end processes, purex process, waste management, safeguards (dose rate for extraction streams), and general support.
Date: September 1, 1977
Partner: UNT Libraries Government Documents Department
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Actinide Partitioning and Transmutation Program. Progress report, April 1--June 30, 1977

Description: Experimental work on the 16 tasks comprising the Actinide Partitioning and Transmutation Program was continued. Summaries of work are given on Purex Process modifications, actinide recovery, Am-Cm recovery, radiation effects on ion exchangers, LMFBR transmutation studies, thermal reactor transmutation studies, fuel cycle studies, and partitioning-transmutation evaluation. (JRD)
Date: October 1, 1977
Creator: Tedder, D. W. & Blomeke, J. O.
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.
Partner: UNT Libraries Government Documents Department
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Improved laboratory assays of Pu and U for SRP purification and finishing processes

Description: Significant improvements have been made in routine assay techniques for uranium and plutonium as part of an effort to improve accountability at the Savannah River Plant (SRP). Emphasis was placed on input/output accountability points and key physical inventory tanks associated with purification and finishing processes. Improvements were made in existing assay methods; new methods were implemented; and the application of these methods was greatly expanded. Prior to assays, samples were validated… more
Date: January 1, 1986
Creator: Holland, M K & Dorsett, R S
Partner: UNT Libraries Government Documents Department
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Rheological evaluation of simulated neutralized current acid waste - transuranics

Description: At the Hanford Plutonium and Uranium Extraction Plant (PUREX), in Richland, Washington, plutonium and uranium products are recovered from irradiated fuel by a solvent extraction process. A byproduct of this process is an aqueous waste stream that contains fission products. This waste stream, called current acid waste (CAW), is chemically neutralized and stored in double shell tanks (DSTs) on the Hanford Site. This neutralized current acid waste (NCAW) will be transported by pipe to B-Plant, a p… more
Date: September 1, 1986
Creator: Fow, C.L.; McCarthy, D.; Thornton, G.T.; Scott, P.A. & Bray, L.A.
Partner: UNT Libraries Government Documents Department
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