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U.S. Department of Energy
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Technology for treatment of salt residue stored at NPPs

Conference ·
OSTI ID:21294652

At Moscow SIA 'Radon', three (3) options for NPP salt residue treatment were developed and tested. Option 1 consists of dissolving the salt residue and subsequent treatment by ozonization, separation of the deposits formed from ozonization and selective cleaning by ferrocyanide sorbents. Option 2 consists of fusion of the salt residue, addition of glass-forming additives and melting of borosilicate glass in a melter such as a 'cold crucible'. Option 3 consists of dissolving the salt residue, oxidation of the solution obtained, removal of radionuclides by collectors and the separate handling of formed deposits and the solution. The deposits containing more than 99 % of the activity are directed to vitrification and the solution is directed either to a concentrates dryer or to cementation. The vitrified waste product is placed in repository for solid radioactive waste storage and the solidified product from the solution goes to an industrial waste disposal site or a repository specially developed at NPP sites for 'exempt waste' products by IAEA classification. (authors)

Research Organization:
WM Symposia, 1628 E. Southern Avenue, Suite 9 - 332, Tempe, AZ 85282 (United States)
OSTI ID:
21294652
Report Number(s):
INIS-US--09-WM-07101
Country of Publication:
United States
Language:
English