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Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

Description: This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - … more
Date: September 1, 1985
Creator: Owen, P. T.; Michelson, D. C. & Knox, N. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status Report on the Argonne Advanced Research Reactor

Description: The interim design and development status is reported. The scope of the work was limited to conceptual design studies supported by critical experiments plus heat transfer and hydraulic tests. Design criteria, facility and site, reactor, core geometry and composition, fuel elements, reflector, core and reflector support structure, reactor vessel, control and instruments, primary coolant systems, secondary coolant system, auxiliary systems, experimental facilities, building layout and constructio… more
Date: November 1, 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NRC plan for cleanup operations at Three Mile Island Unit 2

Description: This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup … more
Date: February 1, 1982
Creator: Lo, R. & Snyder, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, June 1961

Description: An interfacial viseometer was built for use in an interfacial phenomena study. Installation of a 6-in.-ID foam separation column system was completed. The dispersiondrying-sintering characteristics of six low-nitrate batches of thoria sol material were studied. The average effective porosity of the CuO pellets used for reactor helium purification was determined to be 0.0545 for H/ sub 2/ transport and 0.0526 for CO transport. In continuous Zirflex dissolution studies, no H/sub 2/O/sub 2/ decomp… more
Date: January 23, 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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Decontamination of Savannah River Plant H-Area hot-canyon crane

Description: Decontamination techniques applicable to the remotely operated bridge cranes in canyon buildings at the Savannah River Plant (SRP) were identified and were evaluated in laboratory-scale tests. High pressure Freon blasting was found to be the most attractive process available for this application. Strippable coatings were selected as an alternative technique in selected applications. The ability of high pressure Freon blasting plus two strippable coatings (Quadcoat 100 and Alara 1146) to remove … more
Date: January 1, 1985
Creator: Rankin, W N & Sims, J R
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Recovery of plutonium and americium from chloride salt wastes by solvent extraction

Description: Plutonium and americium can be recovered from aqueous waste solutions containing a mixture of HCl and chloride salt wastes by the coupling of two solvent extraction systems: tributyl phosphate (TBP) in tetrachloroethylene (TCE) and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in TCE. In the flowsheet developed, the salt wastes are dissolved in HCl, the Pu(III) is oxidized to the IV state with NaClO/sub 2/ and recovered in the TBP-TCE cycle, and the Am is then removed from t… more
Date: January 1, 1987
Creator: Reichley-Yinger, L. & Vandegrift, G.F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Waste Treatment and Disposal Progress Report for June and July 1961

Description: 7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scaven… more
Date: October 24, 1961
Creator: Blanco, R. E. & Struxness, E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SOLUBLE NEUTRON POISONS AS A PRIMARY CRITICALITY CONTROL IN SHIELDED AND CONTAINED RADIOCHEMICAL FACILITIES

Description: Studies indicated that the use of soluble poisons as a primary criticality control offers economic and other advantages in that it permits the factors of vessel size and shape and solution concentrations to be dictated by considerations other than those of criticality. It is believed that soluble poison criticality control can be made as reliable as other methods of coaditional control if the application is preceded by adequate development work and is monitored by multiple. independent safeguar… more
Date: July 26, 1962
Creator: Nichols, J.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JULY, AUGUST, SEPTEMBER, 1961

Description: Development activities are reported on pyrometallurgical processes including melt refining and those using liquid metal solvents. Development of processing facilities for EBR II is also reported. In other work, laboratory- and engineering-scale investigations on fluoride volatility processes were condueted, and conversion of UF/sub 6/ to UO/sub 2/ was studied. Investigations are also reported concerning the kinetics of metal ignition and oxidation, and metalwater reactions. In work associated w… more
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Westinghouse Hanford Company waste minimization and pollution prevention awareness program plan

Description: The purpose of this plan is to establish the Westinghouse Hanford Company's Waste Minimization Program. The plan specifies activities and methods that will be employed to reduce the quantity and toxicity of waste generated at Westinghouse Hanford Company (Westinghouse Hanford). It is designed to satisfy the US Department of Energy (DOE) and other legal requirements that are discussed in Subsection C of the section. The Pollution Prevention Awareness Program is included with the Waste Minimizati… more
Date: August 1, 1991
Creator: Craig, P.A.; Nichols, D.H. & Lindsey, D.W.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

Description: Activities in research programs are summarized in the areas of power reactor fuel processing, fluoride volatility processing, molten salt reactor fuel processing, homogeneous reactor fuel processing, waste treatment and disposal pilot plant decontamination, GCR coolant purification studies, equipment decontamination, HRP thoria blanket development, fuel cycle development, transuranium element studies, production of U/sup 232/, uranium processing, fission product recovery, thorium recovery from … more
Date: September 21, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interactive planning system for developing decommissioning and decontamination plans at Hanford

Description: The 570-square mile Hanford Project contains facilities with varying degrees of radioactive contamination as a result of plutonium production operations. With the evolution of production requirements and technology, many of these have been retired and will be decommissioned and decontaminated (D and D). Planning for D and D at Hanford requires identification and characterization of contaminated facilities, prioritization of facilities for decommissioning, selection of D and D modes, estimating … more
Date: September 1, 1977
Creator: Litchfield, J. W. & King, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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INEL waste cleanup

Description: Decommissioning and decontamination activities at the Idaho National Engineering Laboratory are discussed. The projects planned and completed are presented. Problems encountered on these projects are discussed. A developmental program is recommended. Contaminated areas consist of test reactors, reactor support facilities, a fuel reprocessing facility and various soil areas. One D and D project in 1960 occurred as a result of an accident at a low-power reactor in which 3 persons were killed, the… more
Date: January 1, 1979
Creator: Chapin, J.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radiological assessment report for the Lansdowne property, 105-107 East Stratford Avenue, Lansdowne, Pennsylvania, October-December 1984

Description: Areas with elevated levels of radioactivity were found throughout both residences, as well as on the surrounding property. Contamination was also found in the garage behind the 105 East structure. The 105 East residence had substantially more contamination than the 107 East residence, as was expected. The chimneys, particularly the rear chimney, from the 105 East residence had extensive contamination, indicating that contaminated materials may have been burned at the site. The high background r… more
Date: September 1, 1985
Creator: Wynveen, R.A.; Smith, W.H.; Sholeen, C.M. & Flynn, K.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Weldon Spring quarry construction staging area and water treatment plant site remedial action characterization report for the Weldon Spring Site Remedial Action Project, Weldon Spring, Missouri

Description: The quarry construction staging area (QCSA) and water treatment plant (WTP) are located in the areas that border the western edge of the Weldon Spring quarry (WSQ). These facilities were constructed to support bulk waste removal from the WSQ. This area was contaminated with U-238, Ra-226, and Th-230 and was remediated prior to construction in order to allow release of the area for use without radiological restrictions. This report documents the methods of characterization, the remediation activ… more
Date: September 1, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RADIOLOGICAL HAZARDS FROM RUPTURE OF THE SECONDARY COOLANT SYSTEM OF THE 10 Mw ESCR

Description: The hazards study was made to determine the radiation level from the secondary sodium lines of the l0-Mw ESCR, and to evaluate the corresponding radioactive concentration in the secondary loop and the maximum permissible effective activation flux in the intermediate heat exchanger. The results are presented graphicallyn the radiation level from the coolant lines during normal operation as a function of line diameter and Na/sup 4/ concentration; the effective thermal neutron activation flux leve… more
Date: January 19, 1960
Creator: Piccot, A.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962

Description: During the report period 110 Mw-hr of operation were completed by LAMPRE I at various power levels, and observations were made of control element performance and reactivity losses. Metallographic examination of a Core I capsule having 120 Mw-hr of irradiation exposure disclosed no major attack. Core II utilizes Ta alloy melts and 13 fuel melts. Starting materials for Core II capsules are tabulated. In research and development a gamma-ray conversion television was used to observe the flow of mol… more
Date: June 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RMDF leach-field decontamination. Final report

Description: The objective of the decontamination effort was to place the Radioactive Materials Disposal Facility (RMDF) leach field in a condition suitable for release for unrestricted use. Radioactively contaminated soil was excavated from the leach field to produce a condition of contamination as low as reasonably achievable (ALARA). The contaminated soil was boxed and shipped to an NRC-licensed burial site at Beatty, Nevada, and to the DOE burial site at Hanford, Washington. The soil excavation project … more
Date: September 15, 1982
Creator: Carroll, J W; Marzec, J M & Stelle, A M
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Post-remedial-action radiological survey of the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pennsylvania, October 1-8, 1981

Description: The post-remedial-action radiological assessment conducted by the ANL Radiological Survey Group in October 1981, following decommissioning and decontamination efforts by Westinghouse personnel, indicated that except for the Advanced Fuels Laboratory exhaust ductwork and north wall, the interior surfaces of the Plutonium Laboratory and associated areas within Building 7 and the Advanced Fuels Laboratory within Building 8 were below both the ANSI Draft Standard N13.12 and NRC Guideline criteria f… more
Date: January 1, 1984
Creator: Flynn, K. F.; Justus, A. L.; Sholeen, C. M.; Smith, W. H. & Wynveen, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Microbial uptake of uranium, cesium, and radium

Description: The ability of diverse microbial species to concentrate uranium, cesium, and radium was examined. Saccharomyces cerevisiae, Pseudomonas aeruginosa, and a mixed culture of denitrifying bacteria accumulated uranium to 10 to 15% of the dry cell weight. Only a fraction of the cells in a given population had visible uranium deposits in electron micrographs. While metabolism was not required for uranium uptake, mechanistic differences in the metal uptake process were indicated. Uranium accumulated sl… more
Date: January 1, 1980
Creator: Strandberg, G. W.; Shumate, S. E., II; Parrott, J. R., Jr. & McWhirter, D. A.
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. 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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