SU1603552A1 - Method for processing liquid radioactive waste - Google Patents

Method for processing liquid radioactive waste

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Publication number
SU1603552A1
SU1603552A1 SU4648863/26A SU4648863A SU1603552A1 SU 1603552 A1 SU1603552 A1 SU 1603552A1 SU 4648863/26 A SU4648863/26 A SU 4648863/26A SU 4648863 A SU4648863 A SU 4648863A SU 1603552 A1 SU1603552 A1 SU 1603552A1
Authority
SU
USSR - Soviet Union
Prior art keywords
solution
radioactive waste
hydrazinenitrate
strontium
nitric acid
Prior art date
Application number
SU4648863/26A
Other languages
Russian (ru)
Inventor
Л.Н. Лазарев
М.Ф. Пушленков
В.А. Бабаин
В.М. Есимантовский
В.А. Старченко
Е.Г. Дзекун
М.В. Гладышев
В.М. Шидловский
Ю.З. Прокопчук
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 SU4648863/26A priority Critical patent/SU1603552A1/en
Application granted granted Critical
Publication of SU1603552A1 publication Critical patent/SU1603552A1/en

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Abstract

FIELD: chemistry, particularly, methods of treating radioactive waste. SUBSTANCE: this method for processing liquid radioactive waste prescribes carrying out extractive treatment of starting aqueous nitrate solution by organic solution of chlorinated cobalt dicarbolide and polyethyleneglycol in diluent, washing resultant extract with nitric acid solution, re-extracting strontium using solution of nitric acid and hydrazinenitrate, and then re-extracting cesium. Disclosed method further prescribes using meta-nitrobenzotrifluoride as carborane complex diluent, admixture of 20 to 60 g/l chlorinated cobalt dicarbolide, 5 to 30 g/l polyethyleneglycol and up to 1 liter of methanitrobenzotrifluoride as organic solution and solution including 2 mol/l nitric acid, 20 to 50 g/l hydrazinenitrate and up to 1 liter of water as strontium re-extractant. EFFECT: greater simplicity and lower rate of consumption of hydrazinenitrate for re-extraction of strontium. 3 cl, 5 tbl
SU4648863/26A 1989-02-07 1989-02-07 Method for processing liquid radioactive waste SU1603552A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
SU4648863/26A SU1603552A1 (en) 1989-02-07 1989-02-07 Method for processing liquid radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SU4648863/26A SU1603552A1 (en) 1989-02-07 1989-02-07 Method for processing liquid radioactive waste

Publications (1)

Publication Number Publication Date
SU1603552A1 true SU1603552A1 (en) 1994-07-30

Family

ID=60527768

Family Applications (1)

Application Number Title Priority Date Filing Date
SU4648863/26A SU1603552A1 (en) 1989-02-07 1989-02-07 Method for processing liquid radioactive waste

Country Status (1)

Country Link
SU (1) SU1603552A1 (en)

Cited By (4)

* 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
US6270737B1 (en) * 1999-12-07 2001-08-07 The United States Of America As Represented By The United States Department Of Energy Extraction processes and solvents for recovery of cesium, strontium, rare earth elements, technetium and actinides from liquid radioactive waste
US6423199B1 (en) 1997-07-17 2002-07-23 British Nuclear Fuels Plc Electrochemical ion exchange using carbollide systems
US7491345B2 (en) * 2004-08-13 2009-02-17 Japan Nuclear Cycle Development Institute Extraction mixture for recovery of actinide elements from acidic solutions

Cited By (5)

* 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
US6270737B1 (en) * 1999-12-07 2001-08-07 The United States Of America As Represented By The United States Department Of Energy Extraction processes and solvents for recovery of cesium, strontium, rare earth elements, technetium and actinides from liquid radioactive waste
US7491345B2 (en) * 2004-08-13 2009-02-17 Japan Nuclear Cycle Development Institute Extraction mixture for recovery of actinide elements from acidic solutions

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