Waste management, radioactive

Radioactive waste is any waste material—gas, liquid, or solid—whose radioactivity exceeds certain limits. These limits have been established by governments or by local authorities, guided by the recommendations of the International Commission on Radiation Protection (ICRP). The ICRP recommendations define the maximum permissible concentration (MPC) for each individual radionuclide and for mixtures of radionuclides in water or air. The U.S. regulation defines such limiting concentration as the radioactivity concentration limit (C), which is the terminology used in this text, Values of C for selected actinides and long-lived fission products in water or air are given in App. D. 

The intention of regulations limiting the release of radioactive material from nuclear installations is to keep the radioactivity concentration in ground and surface water or in air well below the levels recommended by the ICRP. The regulations may foUow either one of two principles or may combine them  

Limitation of the total amount of radioactivity associated with a certain material that may be released over a given period of time 

The techniques of waste management depend largely on the type of waste to be dealt with. The criteria are the level of the radioactivity concentration in the waste, the nature of the 

With respect to the level of radioactivity concentration, several waste classifications are in use appropriate for particular handling schemes. More basic distinctions are between waste that requires radiation shielding and that which does not and between waste that needs to be cooled and that which does not. 

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Radioactive Waste Management A.n IAEA. Source Book, International Atomic Energy Agency, Vienna, Austria, 1992. 

R. E. Berlin and C. C. Stanton, Radioactive Waste Management, John Wiley Sons, Inc., New York, 1989. 

Y. S. Tang and J. H. Saling, Radioactive Waste Management, Hemisphere, New York, 1990. 

The Role of the Monitored Retrievable Storage Facility in an Integrated Waste Management System, DOE/RW-0238, Office of Civihan Radioactive Waste Management, U.S. Department of Energy, Washington, D.C., 1989. 

The Shallow land Burial ofEow-Eevel Radioactively Contaminated Solid Waste, Committee on Radioactive Waste Management, National Academy of Sciences, Washiagton, D.C., 1976. 

Directions in Eow-Eevel Radioactive Waste Management A Brief History of Commercial Eow-Eevel Radioactive Waste Disposal, DOE/LLW-103, Rev. 1, The National Low-Level Waste Management Program, INEL, Idaho Eads, Idaho, Aug. 1994. 

American Nuclear Society, (annual). High Level Radioactive Waste Management Proceedings for the International Topical Meeting of the American Nuclear Society and the American Society of Cavil Engineers. Chicago American Nuclear Society. 

U.S. Department of Energy Office of Civilian Radioactive Waste Management. The Yncca Monntain Project. < http //www.ymp. gov >. 

The Clinton Administration believes that the overriding goal of the Federal Government s high-level radioactive waste management policy should be the establishment of a permanent geologic repository - essential not only for the disposal of commercial spent fuel, but also for... 

The fact that spent fuel reprocessing and recycle are essential components ofgood nuclear non-proliferation and radioactive waste management practices. These actions are needed so that more efficient use can be made offissionablc materials, and unwanted radioactive fission products can be disposed of without need for permanent safeguards. In addition, potential weapons usable materials are destroyed through beneficial use. 

OCWRM, 1998. Viabilily Assessment of a Repository at YuccaMountain, Volume 3 Total System Performance Assessment, DOE/RW-0508/V3, U.S. Department of Energy, Office ofCivilian Radioactive Waste Management, North Las Vegas. 

Y. S. Tang. Ph.D has more than 35 years of experience in the field of thermal and fluid flow. His research interests have covered aspects of thermal hydraulics that are related to conventional and nonconventional power generation systems, with an emphasis on nuclear reactor design and analysis that focuses on liquld-meta -cooled reactors. Dr. Tang is co-author of Radioactive Waste Management published by Taylor 8 Francis, and Thermal Analysis of Liquid Metal Fast Breeder Reactors, He received a B5. from National Central University In China and an MS. in mechanical engineering from the University of Wisconsin. He earned his Ph.D. 

Cohen Y, Cooter EJ (2002) Multimedia environmental distribution of toxics (Mend-Tox). I. Hybrid compartmental-spatial modeling framework. Pract Periodical Hazard Toxic Radioactive Waste Manag 6(2) 70-86... 

Brar SK, Verma M, Surampalli RY, Misra K, Tyagi RD, Meunier N, Blais JF (2006) Bioremediation of hazardous wastes - a review. Prac Period Hazard Tox Radioactive Waste Manag 10 59-72... 

Cadwell, L.L., R.G. Schreckhise, and R.E. Fitzner. 1979. Cesium-137 in coots (Fulica americana) on Hanford waste ponds contribution to population dose and offsite transport estimates. Pages 485-491 in Low-Level Radioactive Waste Management Proceedings of Health Physics Society. Twelfth Midyear Topical Symposium. February 11-15, 1979, Williamsburg, VA. 

Radioactive waste management, 17 547-551 25 850-862 environmental concerns related to,... 

Waste treatment processes. See also Hazardous waste management Radioactive waste management Solid waste management for radioactive waste, 25 853-854 titanium-related, 25 64-65 Waste vitrification process, 12 616 Wastewater, 9 443. See also Effluent treatment... 

Bennett, P. D., Brumbach, B., Farmer, T. W., Funkhouser, P. L., and Hatheway, A. W., 1999, Remedy Selection for Cleanup of Uncontrolled Waste Sites Practical Periodical of Hazardous, Toxic, and Radioactive Waste Management, Vol. 3, No. 1, January, pp. 23-34. 

Hansen, W. J., Orth, K. D., and Robinson, R. K., 1998, Cost Effectiveness and Incremental Cost Analyses Alternative to Benefit-Cost Analysis for Environmental Projects Practice Periodical of Hazardous, Toxic and Radioactive Waste Management, January, pp. 8-12. 

Galluzo, M.J. Baniji, S.K. Bajpai, R. SurampaUi, R.Y. Atrazine removal through hiofiltration. Practice Periodical of Hazardous, Toxic, and Radioactive Waste Manage. 1999, 3, 163. 

Disposal costs at various radioactive waste management facilities in the United States range from 20/ft to 1500/ft. ANL used an average disposal cost of 60/ft of treated waste form to estimate the total disposal costs for the hypothetical Ceramicrete prodnct. The estimated cost was 2836/m of waste. According to the ANL, this fignre is lower than the disposal costs for cement, which were estimated at 3700/m (D20934H, p. 15). 

Miller, W., Hooker, P. Richardson, P. 2003. Natural analogue studies Their application to a repository safety case. Proceedings of the 10th International High-level Radioactive Waste Management Conference (IHLRWM), March 30 to April 3 2003, Las Vegas. 

Stefanovsky, S. V. Dmitriev, S. A. 1995. EPR of radiation centers in ion-implanted glasses simulating vitrified radioative wastes. In Slate, S., Feizollahi, F. Creer, J. (eds) Proceedings of the Fifth International Conference on Radioactive Waste Management and Environmental Remediation. ASME, New York, 1, 409-411. 

Dmitriev, S. A. Stefanovsky, S. V. 2000. Radioactive Waste Management. Mendeleev University... 

Glagolenko, Yu, V., Dzekun, E. G., Drozhko, E. G., Medvedev, G. M., Rovny, S. I. Suslov, A. P. 1996. Radioactive waste management strategy at production association Mayak . Issues of Radiation Safety, 2, 3-10 (in Russian). 

Sobolev, I. A., Dmitriev, S. A. et al. 1998. Application of the cold cmcible technology in radioactive waste conditioning In Proceedings of the Eighth International Conference on High Level Radioactive Waste Management, Las Vegas, 702-704. 

Yudintsev, S. V., Stefanovsky, S. V. Ewing, R. C. 1999. Structural and compositional relationships in titanate-composed ceramics for actinide-bearing waste immobilization. In Proceedings of the 7th International Conference on Radioactive Waste Management and Environmental Remediation ICEM 99. Nagoya, Japan, CD-ROM. 

Kksson, S. E. 1983, The immobilisation of cesium in synroc hollandite. Radioactive Waste Management and the Nuclear Fuel Cycle, 4, 53-72. 

Oversby, V. M. Ringwood, A. E. 1981. Lead isotopic studies of zirconolite and perovskite and their implications for long range synroc stability. Radioactive Waste Management, 1, 289-307. 

Stewart, M. W. A., Begg, B. D. et al. 2003. Ion irradiation damage in zirconate and titanate ceramics for plutonium disposition. Proceedings of ICEM 03 The 9th International Conference on Radioactive Waste Management and Environmental Remediation, in press. 

Radioactive waste management is a quite mature field of application of basic geoscientific disciplines. As we will discuss in forthcoming sections, the long-term performance and henceforth the safety of radioactive waste disposal systems, deeply relies on the basic principles that control the release, mobility, and transport of the chemical elements in the geosphere. In the context of radioactive waste disposal, the waste matrix constitutes the innermost of the barriers that may control the release and ulterior transport of radionuclides through the ground-water systems. 

Merino, J., Cera, E., Bruno, J., Erikssen, T., Quinones, J. Martinez-Esparza, A. 2001. Long term modelling of spent fuel oxidation/ dissolution under repository conditions. ICEM 01. Session 23, V. The 8th International Conference on Radioactive Waste Management and Environmental Remediation. 30 September-4 October 2001, Bruges (Brugge), Belgium. 

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