RU2001123414A - METHOD FOR PROCESSING LIQUID ORGANIC RADIOACTIVE WASTE - Google Patents

METHOD FOR PROCESSING LIQUID ORGANIC RADIOACTIVE WASTE

Info

Publication number
RU2001123414A
RU2001123414A RU2001123414/06A RU2001123414A RU2001123414A RU 2001123414 A RU2001123414 A RU 2001123414A RU 2001123414/06 A RU2001123414/06 A RU 2001123414/06A RU 2001123414 A RU2001123414 A RU 2001123414A RU 2001123414 A RU2001123414 A RU 2001123414A
Authority
RU
Russia
Prior art keywords
extractant
processing liquid
radioactive waste
diluent
liquid organic
Prior art date
Application number
RU2001123414/06A
Other languages
Russian (ru)
Other versions
RU2217824C2 (en
Inventor
Андрей Викторович Воробьев
Вячеслав Николаевич Зубов
Юрий Григорьевич Кривицкий
Владимир Иванович Мацеля
Original Assignee
Горно-химический комбинат
Filing date
Publication date
Application filed by Горно-химический комбинат filed Critical Горно-химический комбинат
Priority to RU2001123414A priority Critical patent/RU2217824C2/en
Priority claimed from RU2001123414A external-priority patent/RU2217824C2/en
Publication of RU2001123414A publication Critical patent/RU2001123414A/en
Application granted granted Critical
Publication of RU2217824C2 publication Critical patent/RU2217824C2/en

Links

Claims (1)

1. Способ переработки жидких радиоактивных отходов, содержащих 30% трибутилфосфата в разбавителе, включающий отделение разбавителя от экстрагента с последующими утилизацией разбавителя и термическим разложением экстрагента, отличающийся тем, что отделение экстрагента от разбавителя проводят путем отгонки с острым паром, термическое разложение ведут при температуре 80-140oС, смешивая экстрагент с пористым материалом в присутствии катализатора при следующем объемном соотношении компонентов:
Экстрагента - 1,0
Пористый материал - 0,4÷1,0
Катализатор - 1,54÷2,0
2. Способ по п. 1, отличающийся тем, что в качестве пористого материала используют активированный уголь.
1. A method of processing liquid radioactive waste containing 30% tributyl phosphate in a diluent, comprising separating the diluent from the extractant followed by disposal of the diluent and thermal decomposition of the extractant, characterized in that the separation of the extractant from the diluent is carried out by steam stripping, thermal decomposition is carried out at a temperature of 80 -140 o With mixing the extractant with a porous material in the presence of a catalyst in the following volumetric ratio of components:
Extractant - 1.0
Porous material - 0.4 ÷ 1.0
Catalyst - 1.54 ÷ 2.0
2. The method according to p. 1, characterized in that activated carbon is used as the porous material.
3. Способ по п. 1, отличающийся тем, что в качестве катализатора используют щавелевую кислоту. 3. The method according to p. 1, characterized in that oxalic acid is used as a catalyst.
RU2001123414A 2001-08-21 2001-08-21 Method for recovery of liquid radioactive wastes RU2217824C2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
RU2001123414A RU2217824C2 (en) 2001-08-21 2001-08-21 Method for recovery of liquid radioactive wastes

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU2001123414A RU2217824C2 (en) 2001-08-21 2001-08-21 Method for recovery of liquid radioactive wastes

Publications (2)

Publication Number Publication Date
RU2001123414A true RU2001123414A (en) 2003-04-20
RU2217824C2 RU2217824C2 (en) 2003-11-27

Family

ID=32026828

Family Applications (1)

Application Number Title Priority Date Filing Date
RU2001123414A RU2217824C2 (en) 2001-08-21 2001-08-21 Method for recovery of liquid radioactive wastes

Country Status (1)

Country Link
RU (1) RU2217824C2 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2593163C1 (en) * 2015-05-14 2016-07-27 Федеральное государственное унитарное предприятие "Горно-химический комбинат" (ФГУП "ГХК") Method for catalytic denitration of liquid radioactive wastes

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