Autor:	V. V. Druzhenkov, E. A. Mezhov, A. N. Sirotinin
Rok vydání:	2002
Předmět:	chemistry.chemical_compound Chemistry Fission Nitric acid Extraction (chemistry) Radiochemistry Radioactive waste chemistry.chemical_element Human decontamination Physical and Theoretical Chemistry Aliquat 336 Spent nuclear fuel Palladium
Zdroj:	Radiochemistry. 44:146-150
ISSN:	1066-3622
DOI:	10.1023/a:1019667128389
Popis:	An extraction process for recovery of fission Pd is proposed. The process parameters are optimized with simulated high-level liquid radioactive waste from nuclear power plants using tri-n-octylamine (TOA) and tricaprylmethylammonium nitrate (Aliquat 336 nitrate) as extractants. The degree of Pd decontamination from fission and corrosion products is estimated and the major interfering components are determined.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::58aecb892a155974805363742cba8acf https://doi.org/10.1023/a:1019667128389 Zobrazit plný text záznamu Full text from SpringerLink