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I. A. Sobolev E. M. Timofeev V. I. Panteleev Yu. V. Karlin V. N. Kropotov Yu. T. Slastennikov V. Yu. Chuikov V. I. Demkin V. T. Rozhkov 《Atomic Energy》1992,73(6):985-988
Moscow Radon Cooperative. Applied Technology Research and Development Institute. Translated from Atomnaya Énergiya, Vol. 73, no. 6, pp. 474-478, December, 1992. 相似文献
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S. A. Dmitriev Yu. V. Karlin M. A. Maryakhin Yu. G. Myasnikov Yu. T. Slastennikov 《Atomic Energy》2009,106(4):266-271
The possibility of concentrating liquid radwastes by evaporation from the surface of porous plates is examined. It is shown
by means of tests of a laboratory setup and an experimental stand that liquid radwastes can be concentrated to salt content
319 g/liter at a temperature far below the evaporation temperature of water and with specific energy consumption 20 times
lower that the specific heat of vaporization of water. The results of the tests of the experimental setup with capacity up
to 43 kg/h with respect to the evaporated water are described; this setup has been incorporated in the EKO mobile modular
water purification complex used at the MosNPO Radon for reprocessing radioactive water from various organizations.
Translated from Atomnaya énergiya, Vol. 106, No. 4, pp. 210–214, April, 2009. 相似文献
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Savkin A. E. Slastennikov Yu. T. Sinyakin O. G. Arustamov A. E. Baldov A. N. 《Radiochemistry》2001,43(3):311-314
It was found that the filtrate yielded by passing bottoms decantates through selective sorbents has the volume activity with respect to 137Cs and 60Co significantly greater than DKb. A pretreatment of the bottoms before selective sorption was tested, which consisted in ozonation and subsequent filtration of the resulting precipitate. By the example of the liquid radioactive waste (LRW) decantate with the highest volume activity, it was shown that by combining the pretreatment with selective sorption it was possible to remove 137Cs, 60Co, and 54Mn radionuclides from the decantate to the level under DKb. Cementation of the slurries in the slurry/cement ratio of 0.3-0.7 was tested. It was proposed that the decantate freed from radionuclides be discharged into the Caspian Sea, and the slurry and secondary wastes yielded by decantate decontamination be included into cement compound. 相似文献
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