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Explosion of cation exchange column in americium recovery service Hanford Plant, August 30, 1976

Description: A cation exchange column in americium recovery service exploded on August 30, 1976 at the Hanford plutonium-finishing plant operated by Atlantic Richfield Hanford Company for the Energy Research and Development Administration at Richland, Washington. The column burst, shattering the glovebox windows. Detectable but small amounts of americium were released from the building in which the explosion occurred. Decontamination efforts and physical repairs to equipment and facilities are estimated to … more
Date: October 8, 1976
Partner: UNT Libraries Government Documents Department
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Partitioning of actinide elements from high-level waste using laser photochemical methods

Description: The feasibility of photochemically fractionating the actinides in nuclear waste processing has been evaluated on a preliminary basis. The data indicate that there are potentially useful photo-redox reactions. However, there is a serious lack of data on photochemical parameters for the solutions conditions which exist in nuclear waste processing. The problem areas relevant to photochemical processing are identified. The experimental areas which must be investigated in order to further evaluate t… more
Date: May 1, 1976
Creator: Gangwer, T
Partner: UNT Libraries Government Documents Department
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Pacific Northwest Laboratory quarterly report to ERDA Nuclear Research and Applications Division, January--March 1976. [Use of /sup 90/SrF/sub 2/ and /sup 137/CsCl WESF capsules as heat sources]

Description: Progress in the strontium heat source and beneficial isotopes utilization programs is discussed. The couples required for the long-term tests compatibility were fabricated and the tests are under way. The 1000-hr tests were completed, and examination of the test couples has been started. Compatibility testing of two full-scale WESF /sup 90/SrF/sub 2/ capsules at 800/sup 0/C has started. Additional short-term compatibility testing of 25 potential containment materials are also under way. The 500… more
Date: April 1, 1976
Creator: Fullam, H. T. & Harmon, K. M.
Partner: UNT Libraries Government Documents Department
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Research and Engineering Division semiannual report. KK Process Development and Technology, November 1, 1975--April 30, 1976. [Pu processing; fractionization; encapsulation; wastes; uptake; hydrology; public protection]

Description: This document is the final semiannual report of the activities supported by KK funds in the areas of process development. These activities have the goal of improving the performance of the ARHC plutonium processing and waste management programs. (DLC)
Date: June 1, 1976
Creator: Manry, C. W. & Cramer, G. W. (eds.)
Partner: UNT Libraries Government Documents Department
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Recovery of americium and curium from nuclear fuel processing waste solutions

Description: Am and Cm exist in the trivalent state under conditions practical in reprocessing, and their chemistry is very similar to that of the rare earths which are present in relatively large amount as major fission products. Conceptual processes to recover Am and Cm, therefore, usually include two separate cycles. The first is the recovery of Am, Cm, and any transcurium actinides, along with the lanthanides, but hopefully separated from all the rest of the fission products and bulk chemicals used in p… more
Date: January 1, 1976
Creator: Campbell, D. O. & Buxton, S. R.
Partner: UNT Libraries Government Documents Department
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Biology of the transuranium elements: an indexed bibliography

Description: This bibliography on the biology of the transuranium elements is a revision of one issued in 1973 (BNWL-1782). It includes essentially all of the citations from the earlier document, a few corrections and additions from the older literature, plus the new literature to mid-1975. It also includes a subject-matter index not present in the original document.
Date: July 1, 1976
Creator: Thompson, R. C. (comp.)
Partner: UNT Libraries Government Documents Department
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Safety analysis report for packaging: neutron shipping cask, model 0. 5T

Description: The Safety Analysis Report for Packaging demonstrates that the neutron shipping cask can safely transport, in solid or powder form, all isotopes of uranium, plutonium, americium, curium, berkelium, californium, einsteinium, and fermium. The shipping cask and its contents are described. It also evaluates transport conditions, structural parameters (e.g., load resistance, pressure and impact effects, lifting and tiedown devices), and shielding. Finally, it discusses compliance with Chapter 0529 o… more
Date: June 11, 1976
Creator: Peterson, R. T.
Partner: UNT Libraries Government Documents Department
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Molten salt extraction of americium from molten plutonium metal

Description: The chemical basis for molten salt extraction separation of americium from plutonium is presented. The extraction factor relationship is used to quantify this liquid-liquid extraction (molten salt-molten metal) unit operation. The amount of salt required for an optimum process is an order of magnitude lower than the amount used previously in the production operation of the process.
Date: March 12, 1976
Creator: Knighton, J. B.; Auge, R. G.; Berry, J. W. & Franchini, R. C.
Partner: UNT Libraries Government Documents Department
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Californium production at the transuranium processing plant. [Transuranium processing plant design, equipment, and facilities]

Description: The Transuranium Processing Plant (TRU) at ORNL, which is the production, storage, and distribution center for the ERDA heavy element research program, is described. About 0.5 percent of /sup 252/Cf is currently being produced. TRU is a hot-cell, chemical processing facility of advanced design. New concepts have been incorporated into the facility for absolute containment, remote operation, remote equipment installation, and remote maintenance. The facilities include a battery of nine heavily s… more
Date: January 1, 1976
Creator: King, L. J.
Partner: UNT Libraries Government Documents Department
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Sorption of curium, berkelium, californium, and einsteinium on cation exchange resin from nitric acid solutions

Description: Plots of the distribution coefficients of curium, berkelium, einsteinium, and californium (+3 ions) adsorbed on Dowex 50-X8 resin from nitric acid solutions are U-shaped, while plots of einsteinium (+4 ions) distribution coefficients are similar to an exponential decay curve. The +3 ions exhibit a minimum sorption at a nitric acid concentration of 6 or 7 molar. (LK)
Date: January 1, 1976
Creator: Chilton, J. M.
Partner: UNT Libraries Government Documents Department
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Observed discrepancies of computer simulated migration of Pu and Am. [In tuff rocks]

Description: Discrepancies between the ion exchange or adsorption model predictions and laboratory model observations on the migration of Pu and Am in porous rocks are elucidated. While the simulation describes the major features well, it does not account for the asymmetric peak shape, etc. Results are explained as due to unsaturated flow. 8 figures. (DLC)
Date: January 1, 1976
Creator: Friedman, A. M.; Fried, S.; Hines, J. & Atcher, R.
Partner: UNT Libraries Government Documents Department
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Migration of plutonium and americium in the lithosphere

Description: When radionuclides are stored as wastes either in permanent repositories or in waste storage areas, the possibility of escape into the environment must be considered. Surface contamination and the transport and migration of radionuclides into the lithosphere through the agency of water are discussed. Water in the form of rain will inevitably wash contaminants into soils and thence into conducting rocks. The migration of radionuclides must follow widely varying paths. In porous rocks, water perc… more
Date: January 1, 1976
Creator: Fried, S.; Friedman, A. M.; Hines, J. J.; Atcher, R. W.; Quarterman, L. A. & Volesky, A.
Partner: UNT Libraries Government Documents Department
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Chemistry of americium

Description: Essential features of the descriptive chemistry of americium are reviewed. Chapter titles are: discovery, atomic and nuclear properties, collateral reading, production and uses, chemistry in aqueous solution, metal, alloys, and compounds, and, recovery, separation, purification. Author and subject indexes are included. (JCB)
Date: January 1, 1976
Creator: Schulz, W. W.
Partner: UNT Libraries Government Documents Department
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Appraisal of available information on uptake by plants of transplutonium elements and neptunium

Description: A critical review was made of reported information from laboratory studies of plant uptake of transplutonic elements plus neptunium. The available data are meager but indicate that the uptake of Np is the greatest followed by Am and Cm. The data are not sufficient to provide recommended values for use in hazard calculations but they do indicate that the actinides other than plutonium will be accumulated in plants to a greater degree than plutonium.
Date: July 1, 1976
Creator: Thomas, R. L. & Healy, J. W.
Partner: UNT Libraries Government Documents Department
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High-purity germanium detection system for the in vivo measurement of americium and plutonium

Description: A high-purity germanium (HPGe) array, photon-counting system has been developed for the Rocky Flats Plant Body-Counter Medical Facility. The newly improved system provides exceptional resolutions of low-energy X-ray and gamma-ray spectra associated with the in vivo deposition of plutonium and americium. Described are the operational parameters of the system and some qualitative results illustrating detector performance for the photon emissions produced from the decay of plutonium and americium … more
Date: September 8, 1976
Creator: Tyree, W. H.; Falk, R. B.; Wood, C. B. & Liskey, R. W.
Partner: UNT Libraries Government Documents Department
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Leaching of irradiated LWR fuel pellets in deionized and typical ground water

Description: Results of leach test experiments on enriched, 5.81 wt percent /sup 235/U, UO/sub 2/ fuel pellet fragments removed from light water reactor (LWR) fuel rods irradiated to an average burnup of 54,450 MWD/MTU are reported. These results are discussed and correlated with similar information about common solidified high-level waste forms. Leach test data were needed to evaluate the relative radiological hazards of storing irradiated fuel rods.
Date: July 1976
Creator: Katayama, Y. B.
Partner: UNT Libraries Government Documents Department
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