Substantiation of the Radiochemical Characteristics of Liquid Radioactive Wastes That Determine Safe Operation of Deep Waste Disposal Sites
Source: Atomic Energy, Volume 94, Number 5, May 2003 , pp. 325-332(8)
The qualitative and quantitative radiochemical composition of liquid wastes is substantiated. This makes possible further safe operation of deep waste disposal sites at the Mining-Chemical Plant and the Siberian Chemical Plant. The toxicity and temperature in a formation with the wastes removed are used as the assessment criteria, satisfaction of which guarantees that the wastes will remain localized within the assigned boundaries of the waste-disposal formation site. It is concluded that the standard limit should be imposed on the specific activity of the long-lived group of radionuclides – 90Sr and 137Cs – rather than on the total specific activity of the wastes placed in deep disposal sites. For maximum specific activity of 90Sr and 137Cs of 37 GBq/dm3 and total specific activity not exceeding 185 GBq/dm3 for buried wastes with radionuclide composition characteristic of modern radiochemical production operations, it is impossible for potentially dangerous radiation and thermochemical processes to occur in the waste-disposal formation site. The recommended limit permits reducing substantially the volume of buried wastes and therefore the region over which the wastes propagate in the deep disposal site.
Document Type: Research Article
Affiliations: 1: Institute of Physical Chemistry, Russian Academy of Sciences 2: State Science Center of the Russian Federation, L. Ya. Karpov Scientific-Research Institute of Physical Chemistry 3: Scientific and Technological University for Nuclear and Radiation Safety, State Atomic Inspection Agency of Russia 4: Ministry of Atomic Energy of the Russian Federation
Publication date: May 1, 2003