SU1589858A1 - Method for isolating metals of acid liquid radioactive wastes and extraction mixture for its realization - Google Patents

Method for isolating metals of acid liquid radioactive wastes and extraction mixture for its realization

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Publication number
SU1589858A1
SU1589858A1 SU4465628/25A SU4465628A SU1589858A1 SU 1589858 A1 SU1589858 A1 SU 1589858A1 SU 4465628/25 A SU4465628/25 A SU 4465628/25A SU 4465628 A SU4465628 A SU 4465628A SU 1589858 A1 SU1589858 A1 SU 1589858A1
Authority
SU
USSR - Soviet Union
Prior art keywords
elements
rare
extraction mixture
radioactive wastes
liquid radioactive
Prior art date
Application number
SU4465628/25A
Other languages
Russian (ru)
Inventor
Л.Н. Лазарев
Е.Г. Дзекун
В.П. Попик
Ю.З. Прокопчук
В.А. Бабаин
И.В. Смирнов
К.А. Петров
Original Assignee
Л.Н. Лазарев
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Л.Н. Лазарев filed Critical Л.Н. Лазарев
Priority to SU4465628/25A priority Critical patent/SU1589858A1/en
Application granted granted Critical
Publication of SU1589858A1 publication Critical patent/SU1589858A1/en

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Abstract

FIELD: hydrometallurgy. SUBSTANCE: cesium and/or strontium and/or rare-earth elements and actinide elements are extracted of liquid radioactive wastes which contains 0.5-3 M nitric acid. Then phases are separated, rare-earth elements, actinide elements and strontium are reextracted. The process is followed by reextraction of cesium with the help of 3-6 M nitric acid solution. Extraction mixture contains chlorinated dicarbollide of cobalt and phosphorous-containing polyethylene glycol ( their concentrations being 0.05-3 M and 0.02-0.2 M respectively ) in nitroaromatic diluent. EFFECT: increases extraction degree of rare-earth and actinide elements, increases capacity of organic phase in relation to extracted elements, decreases their concentration in solution. 4 cl, 4 tbl
SU4465628/25A 1988-07-21 1988-07-21 Method for isolating metals of acid liquid radioactive wastes and extraction mixture for its realization SU1589858A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
SU4465628/25A SU1589858A1 (en) 1988-07-21 1988-07-21 Method for isolating metals of acid liquid radioactive wastes and extraction mixture for its realization

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SU4465628/25A SU1589858A1 (en) 1988-07-21 1988-07-21 Method for isolating metals of acid liquid radioactive wastes and extraction mixture for its realization

Publications (1)

Publication Number Publication Date
SU1589858A1 true SU1589858A1 (en) 1994-07-30

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Family Applications (1)

Application Number Title Priority Date Filing Date
SU4465628/25A SU1589858A1 (en) 1988-07-21 1988-07-21 Method for isolating metals of acid liquid radioactive wastes and extraction mixture for its realization

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SU (1) SU1589858A1 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6258333B1 (en) * 1999-02-23 2001-07-10 The United States Of America As Represented By The United States Department Of Energy Method for the simultaneous recovery of radionuclides from liquid radioactive wastes using a solvent
US6423199B1 (en) 1997-07-17 2002-07-23 British Nuclear Fuels Plc Electrochemical ion exchange using carbollide systems

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6423199B1 (en) 1997-07-17 2002-07-23 British Nuclear Fuels Plc Electrochemical ion exchange using carbollide systems
US6258333B1 (en) * 1999-02-23 2001-07-10 The United States Of America As Represented By The United States Department Of Energy Method for the simultaneous recovery of radionuclides from liquid radioactive wastes using a solvent
US6468445B2 (en) 1999-02-23 2002-10-22 The United States Of America As Represented By The United States Department Of Energy Solvent for the simultaneous recovery of radionuclides from liquid radioactive wastes

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