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De Beer, G.P.; Steenkamp, H.C.; Van Niekerk, S.E.; Liebenberg, G.R.; De Beer, L.; Strydom, G.J.
35. annual SAAPMB congress and summer school1995
35. annual SAAPMB congress and summer school1995
AbstractAbstract
[en] Short communication
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South African Association of Physicists in Medicine and Biology, Pretoria (South Africa); 117 p; May 1995; p. 72; 35. annual SAAPMB congress and summer school; Cape Town (South Africa); 9-12 May 1995; Available from The Dept. of Medical Physics, Medical Univ. of Southern Africa, P.O. Box 146, Medunsa, 0204, South Africa
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Miscellaneous
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Kennedy, W.E. Jr.; Hill, R.L.; Aaberg, R.L.; Wallo, A. III
Pacific Northwest Lab., Richland, WA (United States). Funding organisation: USDOE, Washington, DC (United States)1994
Pacific Northwest Lab., Richland, WA (United States). Funding organisation: USDOE, Washington, DC (United States)1994
AbstractAbstract
[en] Pacific Northwest Laboratory (PNL) is conducting technical analyses to support the US Department of Energy (DOE), Office of Environmental Guidance, Air, Water, and Radiation Division (DOE/EH-232) in developing radiological control criteria for recycling or reuse of metals or equipment containing residual radioactive contamination from DOE operations. The criteria, framed as acceptable concentrations for release of materials for recycling or reuse, are risk-based and were developed through analysis of generic radiation exposure scenarios and pathways. The analysis includes evaluation of relevant radionuclides, potential mechanisms of exposure, and non-health-related impacts of residual radioactivity on electronics and film. The analysis considers 42 key radionuclides that DOE operations are known to generate and that may be contained in recycled or reused metals or equipment. Preliminary results are compared with similar results reported by the International Atomic Energy Agency, by radionuclide grouping
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Nov 1994; 14 p; Residual radioactivity and recycling workshop; Mito (Japan); 9-11 Nov 1994; CONF-9411170--1; CONTRACT AC06-76RL01830; Also available from OSTI as DE95004906; NTIS; US Govt. Printing Office Dep
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Report
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Krause, G.; Lorenzen, J.; Lindberg, M.; Olsson, L.; Wirendal, B.
KONTEC 2003: 6. international symposium - Conditioning of radioactive operational and decommissioning wastes, including 6. status report of BMBF 'Decommissioning and dismantling of nuclear facilities'. Proceedings2003
KONTEC 2003: 6. international symposium - Conditioning of radioactive operational and decommissioning wastes, including 6. status report of BMBF 'Decommissioning and dismantling of nuclear facilities'. Proceedings2003
AbstractAbstract
[en] Radioactive contaminated waste is a great cost factor for nuclear power plants and other nuclear industry. On the deregulated electricity market the price on produced kWh is an important competition tool. Therefore the waste minimisation and volume reduction has given highest priority by many power producers in the process to achieve savings and hence low production cost. Studsvik RadWaste AB in Nykoeping, Sweden, is a company specialised in volume reduction of LLW, as solid combustible waste and as scrap metal for melting and recycling. The treatment facility in Sweden offers this kind of services - together with segmentation and decontamination when necessary - for several customers from Europe, Japan and USA. In addition to these treatment services a whole spectrum of services like transportation, measurement and safeguard, site assistance, industrial cleaning and decontamination in connection with demolition at site is offered from the Studsvik company. (orig.)
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KONTEC Gesellschaft fuer technische Kommunikation mbH, Hamburg (Germany); Kerntechnische Gesellschaft e.V., Bonn (Germany). Fachgruppe Stillegung; 972 p; ISBN 3-9806415-6-2; ; 2003; p. 798-802; KONTEC 2003: 6. international symposium - Conditioning of radioactive operational and decommissioning wastes, including 6. status report of BMBF 'Decommissioning and dismantling of nuclear facilities'; KONTEC 2003: 6. internationales Symposium - Konditionierung radioaktiver Betriebs- und Stillegungsabfaelle, einschliesslich 6. Statusbericht des BMBF 'Stilllegung und Rueckbau kerntechnischer Anlagen'; Berlin (Germany); 19-21 Mar 2003; Available from TIB Hannover
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AbstractAbstract
[en] Processes are introduced which in the meantime have matured to a degree which makes possible the safe management of metallic residual materials from the nuclear sphere. Obviously the improvement of decontamination processes and, in particular, the advancement of measurement techniques in the sense of a high degree of free measurement automation with reproducible results, has a major potential for development, in particular with regard to pollutant-free recycling by decontamination. (orig.)
[de]
Es werden Verfahren vorgestellt, die inzwischen soweit ausgereift sind, dass eine sichere Entsorgung der metallischen Reststoffe aus dem kerntechnischen Bereich gegeben ist. Ein erhebliches Entwicklungspotential steckt offensichtlich, insbesondere bei der schadlosen Wiederverwertung durch Dekontamination noch in einer Verbesserung der Dekontaminationsverfahren und insbesondere in einer Weiterentwicklung der Messtechnik im Sinne einer weitgehend automattisierten Freimessung mit reproduzierbaren Ergebnissen. (orig.)Original Title
Schadstofflose Wiederverwertung von metallischen Reststoffen
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Kernforschungszentrum Karlsruhe GmbH (Germany); Hannover Univ. (Germany). Inst. fuer Werkstoffkunde; 210 p; 1992; p. 163-181; 2. decommissioning colloquium: Decommissioning and dismantling of the Greifswald nuclear plants; 2. Stillegungskolloquium: Stillegung und Abbau der Kernkraftwerke Greifswald; Hannover (Germany); 19-20 Nov 1992; Available from FIZ Karlsruhe
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Miscellaneous
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Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.
Pacific Northwest Lab., Richland, WA (United States). Funding organisation: USDOE, Washington, DC (United States)1995
Pacific Northwest Lab., Richland, WA (United States). Funding organisation: USDOE, Washington, DC (United States)1995
AbstractAbstract
[en] Pacific Northwest Laboratory is providing Environmental Protection Support and Assistance to the USDOE, Office of Environmental Guidance. Air, Water, and Radiation Division. As part of this effort, PNL is collecting data and conducting technical evaluations to support DOE analyses of the feasibility of developing radiological control levels for recycling or reuse of metals, concrete, or equipment containing residual radioactive contamination from DOE operations. The radiological control levels will be risk-based, as developed through a radiation exposure scenario and pathway analysis. The analysis will include evaluation of relevant radionuclides, potential mechanisms of exposure, and both health and non-health-related impacts. The main objective of this report is to develop a methodology for establishing radiological control levels for recycle or reuse. This report provides the results of the radiation exposure scenario and pathway analyses for 42 key radionuclides generated during DOE operations that may be contained in metals or equipment considered for either recycling or reuse. The scenarios and information developed by the IAEA. Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities, are used as the initial basis for this study. The analyses were performed for both selected worker populations at metal smelters and for the public downwind of a smelter facility. Doses to the public downwind were estimated using the US (EPA) CAP88-PC computer code with generic data on atmospheric dispersion and population density. Potential non-health-related effects of residual activity on electronics and on film were also analyzed
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Jul 1995; 164 p; CONTRACT AC06-76RL01830; Also available from OSTI as DE95016636; NTIS; US Govt. Printing Office Dep
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AbstractAbstract
[en] Bench-top feasibility studies with Hanford single-shell tank (SST) simulants, using a new low-temperature (50-60 degrees C) process for converting nitrate to ammonia and ceramic, have conclusively shown that between 90 and 99% of the nitrate at Hanford can be readily converted to ammonia. In this process, aluminum powders or shot can be used to convert alkaline, nitrate-based supernate to ammonia and an alumina-silica-based ceramic solid. The process may actually be able to utilize already contaminated aluminum scrap metal from various US DOE sites to effect the conversion. The final nitrate-free ceramic product can be calcined, pressed, and sintered like any other ceramic. Based upon the starting volumes of 6.2 and 3.1 M sodium nitrate solution (probable supernate concentrations resulting from salt-cake/sludge removal from the Hanford SSTs), volume reductions as high as 70% are currently obtained, compared with an expected 40 to 50% volume increase if the Hanford supernate were grouted. Engineering data extracted from bench-top studies indicate that the process will be very economical. These data were used to cost a batch facility with a production rate of 1200 kilograms of nitrate per hour for processing all the Hanford SST waste over 20 years. Our process cost analysis indicates that between $2.01 and 2.66 will be required to convert each kilogram of nitrate. Based upon 1957 literature, these costs are one-third to one-half of the processing costs quoted for electrolytic and thermal processes
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Mighissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E. (Temple Univ., Philadelphia, PA (United States). Dept. of Environmental Safety and Health) (eds.); American Society of Mechanical Engineers, New York, NY (United States). Mixed Waste Committee; Temple Univ., Philadelphia, PA (United States). Dept. of Environmental Safety and Health; 817 p; 1993; p. 1.1.1-1.1.11; 2. international mixed waste symposium; Baltimore, MD (United States); 17-20 Aug 1993; Also available from OSTI as DE94012383; NTIS; US Govt. Printing Office Dep
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Thompson, R.S.
Savannah River Site (SRS), Aiken, SC (United States). Funding organisation: DOE (United States)1999
Savannah River Site (SRS), Aiken, SC (United States). Funding organisation: DOE (United States)1999
AbstractAbstract
[en] 'Plutonium scrap from another Department of Energy site is to be converted at Savannah River Site (SRS) to a form for permanent storage. For accountability and criticality safety, the material must be measured at SRS, and handling restrictions require assay in 9975 shipping drums. A Multiplicity Neutron Counter is available to perform the measurements, but requires about 12 hours per assay, too long to support the measurement schedule. The assay time has been reduced to 2 hours by use of the Known-M method, the first known routine application of Known-M. The approach involves expression of the multiplication in terms of the effective 239Pu mass and a quadratic polynomial. Because only a few measured values of multiplication were available, values from Monte Carlo neutron transport calculations (using code MCNP) were used. Because the scrap cans have variable fill heights and fill height affects multiplication, an algorithm to correct the effective 239Pu mass values for that effect was developed. Testing of the Known-M calibration with limited data suggests a 2-sigma uncertainty of about 5 percent. Drums can contain one or two individual scrap cans, and an algorithm for measuring the combined plutonium content in two cans was developed. The Known-M assay calculations will be performed off line using a spreadsheet.'
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22 Jul 1999; [vp]; 40. meeting of the Institute of Nuclear Materials Management; Phoenix, AZ (United States); 26-29 Jul 1999; CONTRACT AC09-96SR18500; Available from OSTI; NTIS; URL:http://www.srs.gov/general/sci-tech/fulltext/ms9900137/ms9900137.pdf; US Govt. Printing Office Dep
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AbstractAbstract
[en] The Fernald plant, formerly known as the Feed Materials Production Facility, is located on a 1050-acre site 17 miles northwest of downtown Cincinnati, Ohio. Site construction was initiated in 1951 to fabricate uranium metal to meet defense production requirements of the U.S. Department of Energy (DOE). In October 1990, the DOE transferred management responsibility for the site from its Defense Programs organization to the Office of Environmental Restoration and Waste Management. In August 1991, the site was renamed the Fernald Environmental Management Project (FEMP) to reflect the site's new cleanup mission. During 40 yr of plant operation, a scrap metal storage area grew to contain 5000 t of scrap metal. Material in the pile, such as structural steel, crushed drums, tanks, and pipes, is contaminated with uranium to levels up to 200,000 disintegrations per minute alpha. In July 1991, cleanup of this pile was designated a CERCLA removal action under the Comprehensive Environmental Response, Compensation, and Liability Act and a consent agreement executed between the DOE and the U.S. Environmental Protection Agency
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American Nuclear Society (ANS) winter meeting; San Francisco, CA (United States); 14-18 Nov 1993; CONF-931160--
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AbstractAbstract
[en] Despite the fact that the use of radiation technologies has always been subjected to strict controls in most countries, the presence of radioactive materials in scrap has been detected relatively often in recent years. This has led to the implementation of a series of international initiatives aimed at detecting and preventing illicit international trafficking with radioactive material, intentional or otherwise. The Spanish iron and steel industry is one of the most important industrial sectors in the country, and depends to a large extent on the importing of a significant proportion of the scrap its uses as raw material. Experience has shown that that countries that import large quantities of scrap should complement the aforementioned international initiatives with others of national scope, in order to reduce the risks arising from the presence of radioactive material in scrap. In this context, the Spanish radiological protection authorities, along with the business associations involved in the metal recovery and smelting industry, have established a national system for the radiological surveillance and control of scrap and of the products resulting from its processing. The system consists of a set of legal bases, the installation of specific radiological surveillance equipment and the enhancement of other general purpose equipment that existed prior to these initiatives, the development of radiological training and information plans for the professionals involved in the metal recovery and smelting sectors and improvement to the national radiological emergency response system. (author)
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International Atomic Energy Agency, Vienna (Austria); 502 p; Aug 2001; p. 362-370; International conference of national regulatory authorities with competence in the safety of radiation sources and the security of radioactive materials; Buenos Aires (Argentina); 11-15 Dec 2000; IAEA-CN--84/67; ISSN 1563-0153;
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AbstractAbstract
[en] The National Council on Radiation Protection and Measurements published NCRP Report No. 141 on November 19, 2002. Contract DE-FG02-98CH10945 provided the sole support for this report titled ''Managing Potentially Radioactive Scrap Metal.'' Some preliminary work supported by the U.S. Environmental Protection Agency that led to an NCRP Letter Report provided some background information for this work. NCRP Report No. 141 provides recommendations on the methodologies and techniques available to the United States for disposing of radioactive, contaminated scrap metals
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19 Nov 2002; 233 p; FG02-98CH10945; Available from NCRP, 7910 Woodmont Avenue, Suite 400, Bethesda, MD 20814 (US)
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