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Wastes, radioactive liquid

Essington EH, Fowler EB, Polzer WL. 1981. The interactions of low-level, liquid radioactive wastes with soils 2. Differences in radionuclide distribution among four surface soils. Soil Sci 132(1) 13-18. [Pg.236]

Halford, D.K., O.D. Markham, and G.C. White. 1983. Biological elimination rates of radioisotopes by mallards contaminated at a liquid radioactive waste disposal area. Health Phys. 45 745-756. [Pg.1742]

The vendor claims that this technology will have four basic applications (1) on-site stabilization of high-level liquid radioactive waste (2) development of cheaper thermal and electrical energy sources (3) creation of scarce elements from more plentiful elements and (4) design and fabrication of table-top particle accelerators. [Pg.541]

Potential applications for CA-CDI technology include the purification of boiler water for fossil and nuclear power plants, volume reduction of liquid radioactive waste, treatment of agricultural wastewater containing pesticides and other toxic compounds, creation of ultrapure water for semiconductor processing, treatment of wastewater from electroplating operations, desalination of seawater, and removal of salt from water for agricultural irrigation. [Pg.746]

Nikiforov, A. S., Kulichenko, V. V. Zhikharev, M. I. 1985. Conditioning of Liquid Radioactive Wastes. Energoatomizdat, Moscow (in Russian). [Pg.60]

Vlasov, V. I., Kedrovsky, O. L., Polyakov, A. S. Shishtchitz, I. Y. 1987. Handling of liquid radioactive waste from the closed nuclear fuel cycle. In Back End of the Nuclear Fuel Cycle Strategies and Options. IAEA, Vienna, 109-117. [Pg.62]

The use of inorganic ion exchangers to solidify liquid radioactive waste followed by pressure sintering to produce a ceramic waste form appears to be a viable alternative to calcina-tion/vitrification processes. Both the process and waste form are relatively insensitive to changes in the composition of the waste feed. The stability of the ceramic waste form has been shown to be superior to vitrified wastes in leaching studies at elevated temperatures. Further studies on the effects of radiation and associated transmutation and the influence of temperature regimes associated with potential geologic repositories are needed for a more definitive comparison of crystalline and amorphous waste forms. [Pg.146]

Field Studies. We have attempted to compare the relative availability of actinides to small mammals living in contaminated environments near ORNL. Shrews, rats and mice have been collected from a 30 year old contaminated floodplain forest ecosystem ( ). Cotton rats (Sigmodon hispidus) have been collected from the banks of a former liquid radioactive waste pond which contains Pu, Am and Cu in sediments and shoreline vegetation. Analyses were performed by isotope dilution mass spectrometry (U, Th and Pu) or by alpha spectrometry (Pu, Am and Cm). [Pg.250]

Two types of containers should be available for disposal purposes. One should be labeled Liquid Radioactive Waste and used for all waste solutions the other, Solid Radioactive Waste, for blotter paper, broken glassware, etc. Liquid wastes must not be poured down any drain, nor solid wastes deposited in normal trash cans. [Pg.186]

Time consuming, expensive, and generates a lot of liquid radioactive waste. [Pg.165]

Use Plexiglas shields when working directly with the radioisotope. Cover your work surface with absorbent paper to localize any spills that may occur. Consult the laboratory instructor for the proper disposal of the solid and liquid radioactive waste that will be produced in this experiment. [Pg.364]

All the NPPs have their own systems for managing the solid and liquid radioactive waste generated at the site. The very low level waste (VLLW) and the low and intermediate level short lived radioactive waste (L IL SL) waste is eonditioned in accordance with the waste acceptance criteria for the landfill type and the SFR repository respectively. Standard techniques are used processing liquid and solid waste. Cement and bitumen are used as matrix for conditioning. [Pg.49]

SNF reprocessing and management of Solid and Liquid Radioactive Waste (SRW and LRW) generated during complex decommissioning of NSs. [Pg.76]

Liquid radioactive waste processing barge and sectors for low-level radioactive waste conditioning and storage and... [Pg.107]

The Coastal Maintenance Base (CMB) in Gorbushechya Bay, Kamchatka, by now transferred under the jurisdiction of the Russian Federal Agency for Atomic Energy (Rosatom) for environmental remediation, was initially designed to accept and store temporarily Solid Radioactive Waste (SRW) neither acceptance nor storage of SNF/Liquid Radioactive Waste (FRW) was provided at the CMB at all. [Pg.170]

MODULE COMPLEX TO PROCESS LOW-ACTIVE LIQUID RADIOACTIVE WASTE... [Pg.229]

FSV Lepse"" has storage for Spent Fuel Assemblies (SFAs), tanks for Liquid Radioactive Waste (LRW) and working area for process operations with reactor equipment. Since 1981 FSV Lepse " has been only used for storage of SFAs, RW, fittings and gears. [Pg.266]

From the above table it follows that major works in different areas are to be performed in Gremikha including -management of SNF of Nuclear Submarines (NSs) with Liquid-Metal Coolant (LMC) reactors and WER -management of Solid and Liquid Radioactive Waste (SRW and LRW) -removal of SNF and Spent Removable Units (SRUs) to Mayak for reprocessing -rehabilitation of buildings, constructions, terrestrial and aquatic systems. [Pg.319]

Removal of solid-phase surface radioactive contamination with no liquid radioactive waste generation... [Pg.385]

The real application of this process is the recalcination of lime sludges from water treatment plants, coking of heavy residues and tars from petroleum refinery operations, concentration and volume reduction of liquid, radioactive wastes, and treatment of refinery sludges containing hydrocarbons, phosphorus, and compounds of calcium, magnesium, iron, and aluminum. [Pg.73]

This section aims to explain the unique features of membrane separation methods, their superior performance in contaminant removal, and their operational sensitivities and limitations. We focus particularly on the factors that need to be carefully assessed when the membrane technology to be used in the treatment of liquid radioactive waste is being considered. These include membrane configuration and arrangement, process application, operational experience, data related to key performance parameters, and plant and organizational impacts. [Pg.824]

IAEA Technical Reports Series No. 431. 2005. Application of Membrane Technologies for Liquid Radioactive Waste Processing, pp. 1-145. Consultants Pabby A.K., Kohout R. (Canada), and TapseU G. (AustraUa) [http /www.iaea.org/Publications/index.html]. [Pg.825]

Sengupta, S.K., Slade, J.A., and Tulk, W.S., Liquid radioactive waste processing with crossflow microflltration and spiral wound reverse osmosis, Report AECL-11270, Chalk River, Ontario, February 1995. [Pg.840]

Rauzen, F. et al., Use of ion exchange and electrodialysis for purification of liquid radioactive wastes. Aiomnaya Ehnergiya, 45,49, 1978, English translation in Soviet J. Atomic Energy 45, 705, 1978. [Pg.841]


See other pages where Wastes, radioactive liquid is mentioned: [Pg.842]    [Pg.1716]    [Pg.234]    [Pg.1762]    [Pg.17]    [Pg.129]    [Pg.1122]    [Pg.976]    [Pg.183]    [Pg.172]    [Pg.345]    [Pg.467]    [Pg.12]    [Pg.66]    [Pg.229]    [Pg.240]    [Pg.245]    [Pg.261]    [Pg.399]    [Pg.25]    [Pg.455]    [Pg.824]   
See also in sourсe #XX -- [ Pg.824 , Pg.850 , Pg.856 , Pg.862 , Pg.866 , Pg.872 ]




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