Main trends in the search for methods for reliable isolation of radioactive waste in the USSR

Kedrovskii, O. L.; Shishchits, I. Yu.; Leonov, E. A.; Spitsyn, V.I.; Balukova, V. D.; Savushkina, M. K.; Sinitsyna, G.S.; Krivokhatskii, A.S.

doi:10.1007/bf01123597

Cited by 5 publications

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“…Thus, the products of solidification of sea-salt concentrates by cementing with clay as a sorption aid are at least as good as bitumen compounds with respect to the fixation strength not only for cesium but also for NaCl. At the same time, it is believed that in clay rocks the diffusion coefficient should not exceed 3⋅10 −1 cm 2 /day for NaCl and 1⋅10 −3 cm 2 /day for cesium for safe disposal of solidified wastes directly in soil [8]. When cement blocks are stored directly in 200-liter barrels, their volume-to-surface area ratio will be 10 cm 3 /cm 2 .…”

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Solidification of radioactive sea-salt concentrates in a modular cementing facility

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The paper is devoted to the solidification of radioactive sea-salt concentrates in a modular cementing facility yielding 200-liter cement blocks. The solidified products with Cambrian clay added as a sorption aid satisfy with respect to the mechanical strength and radionuclide leaching the domestic and foreign requirements for safe storage in standard and very simple disposal sites.Liquid radioactive wastes which often contain sea salts in substantial amounts are formed during the operation of propulsion nuclear power systems (NPSs). Floating facilities for reprocessing radioactive waters (the special tankers Amur in the Northern fleet and Pinega in the Pacific Ocean Fleet) were provided for reprocessing radioactive water. The plan was to incorporate the radioactive concentrates into bitumen compounds using the proposed technology [1]. However, because the bituminization process presents a danger of fire and explosion and the solidified products are plastic and combustible (the flash point is below 300°C) it is being replaced by the technologically simpler, safer, and less energy intensive cementing process.Cementing for solidifying radioactive concentrates by simple mixing of the components makes it possible to obtain strong and noncombustible products which retain their integrity even in shipping accidents. For example, cement blocks do not lose their shape after standing for 30 min at 800°C, and since their mechanical strength is 10 MPa they remain whole when dropped from a height of 9 m [2]. However, cement compounds do not fix radionuclides nearly as strongly as bitumen compounds.Sodium chloride (NaCl), which determines the salt content of sea waters, does not interact chemically with bitumen.

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“…This will reduce the disposal costs substantially. Because of their weak water perme- ability (up to 1·10 −3 m/day) and good sorption properties (above 10 mg-equiv per 100 g), clay soils prevent not only radionuclides (the distribution coefficient for 137 Cs is 800) but also the salt components of the wastes (NaCl) from spreading [8].…”

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Solidification of radioactive sea-salt concentrates in a modular cementing facility

et al. 2007

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“…Also, man-made barriers and packages are required, at least through final disposal. A sketch of a conceptual deep disposal repository is given in the reference (Kedrovskiy et al 1987).…”

Section: • Disposal Of Consolidated Wastes In Underground Excavationsmentioning

confidence: 99%

“…Near-surface disposal concepts for LLW and ILW have been studied that included the potential use of "pits" (Kedrovskiy et al 1987).…”

Section: Research and Developmentmentioning

confidence: 99%

“…Interim storage of solidified intermediate-level wastes is planned prior to disposal (Semenov 1983); however, it has been acknowledged that low-and intermediate-level wastes have been disposed of by injection into wells from the 1960s at least through 1980 (GKAE 1978 p. 9-10;Kondratyev 1976;Spitsyn 1978;BBC 8/1/80). Placing solidified HLW [and possibly some ILW] in a deep geologic formation has been considered as the likely disposal method (Kedrovskiy et al 1987} and a site for a HLW repository may be identified next year (Nucleonics Week I0/89a). Stage VI final disposal of solidified waste at centralized or regional disposal sites (Sedov et al 1983(Sedov et al , 1988).…”

Section: Policy and Strategymentioning

confidence: 99%

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Radioactive waste management in the USSR: A review of unclassified sources

Bradley¹

1991

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Principles of site selection for underground burial of solidified radioactive wastes

Kedrovskii¹,

Shishchits²,

Leonov³

1989

At Energy

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Main trends in the search for methods for reliable isolation of radioactive waste in the USSR

Cited by 5 publications

References 0 publications

Solidification of radioactive sea-salt concentrates in a modular cementing facility

Solidification of radioactive sea-salt concentrates in a modular cementing facility

Radioactive waste management in the USSR: A review of unclassified sources

Principles of site selection for underground burial of solidified radioactive wastes

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