JPS6463899A - Treatment of radioactive waste liquid containing sodium nitrate - Google Patents

Treatment of radioactive waste liquid containing sodium nitrate

Info

Publication number
JPS6463899A
JPS6463899A JP22069387A JP22069387A JPS6463899A JP S6463899 A JPS6463899 A JP S6463899A JP 22069387 A JP22069387 A JP 22069387A JP 22069387 A JP22069387 A JP 22069387A JP S6463899 A JPS6463899 A JP S6463899A
Authority
JP
Japan
Prior art keywords
waste liquid
radioactive waste
treatment
containing sodium
liquid containing
Prior art date
Legal status (The legal status 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 status listed.)
Pending
Application number
JP22069387A
Other languages
Japanese (ja)
Inventor
Isao Kondo
Katsuyuki Otsuka
Yoshiharu Takahashi
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Power Reactor and Nuclear Fuel Development Corp
Original Assignee
Power Reactor and Nuclear Fuel Development Corp
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 Power Reactor and Nuclear Fuel Development Corp filed Critical Power Reactor and Nuclear Fuel Development Corp
Priority to JP22069387A priority Critical patent/JPS6463899A/en
Publication of JPS6463899A publication Critical patent/JPS6463899A/en
Pending legal-status Critical Current

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  • Heat Treatment Of Water, Waste Water Or Sewage (AREA)

Abstract

PURPOSE:To eliminate a hazard of a fire and considerably reduce the volume of producing quantity of solidified materials by changing radioactive waste liquid into calcium sulfate to treat. CONSTITUTION:Sulfuric acid in excess of 5-10% of the quantity necessary for reaction is added, mixed and agitated in radioactive waste liquid containing sodium nitrate, heated in the condition that the ratio of TBP is 0.12% or less at 135 deg.C or less, the nitric acid is removed and radioactive waste liquid containing sodium sulfate is made. Calcium hydroxide or calcium oxide is added, mixed and agitated in the waste liquid. Heating treatment is performed to separate solid and liquid each other if necessary. Solid calcium sulfate is kept at it is or forming material is mixed therewith to solidify as after-treatment. Liquid sodium hydroxide solution is separated from accompanying alkali metal in a purifying process. The remaining sodium is collected and used again. Therefore, since heating materials are not used, the volume of production of solidified materials can be reduced and economical efficiency is improved.
JP22069387A 1987-09-03 1987-09-03 Treatment of radioactive waste liquid containing sodium nitrate Pending JPS6463899A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP22069387A JPS6463899A (en) 1987-09-03 1987-09-03 Treatment of radioactive waste liquid containing sodium nitrate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP22069387A JPS6463899A (en) 1987-09-03 1987-09-03 Treatment of radioactive waste liquid containing sodium nitrate

Publications (1)

Publication Number Publication Date
JPS6463899A true JPS6463899A (en) 1989-03-09

Family

ID=16755008

Family Applications (1)

Application Number Title Priority Date Filing Date
JP22069387A Pending JPS6463899A (en) 1987-09-03 1987-09-03 Treatment of radioactive waste liquid containing sodium nitrate

Country Status (1)

Country Link
JP (1) JPS6463899A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9739545B2 (en) 2009-12-04 2017-08-22 G.M.A. Srl Method for coating a mechanical member, and mechanical member thus coated
CN109830324A (en) * 2019-01-17 2019-05-31 中国辐射防护研究院 A kind of charging feed liquid and preparation method suitable for pyrolytic incineration method processing Radioactive myocardial damage
CN110975613A (en) * 2019-12-04 2020-04-10 沈阳环境科学研究院 Regeneration method of sodium-alkali desulfurizing agent
CN115105857A (en) * 2021-03-23 2022-09-27 郑州天一萃取科技有限公司 Purifying treatment agent and purifying method for tributyl phosphate waste organic phase

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5265178A (en) * 1975-11-25 1977-05-30 Mitsui Eng & Shipbuild Co Ltd Treating method of waste fluid containing sodium nitrate
JPS61182599A (en) * 1985-02-08 1986-08-15 株式会社日立製作所 Method of treating radioactive waste liquor

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5265178A (en) * 1975-11-25 1977-05-30 Mitsui Eng & Shipbuild Co Ltd Treating method of waste fluid containing sodium nitrate
JPS61182599A (en) * 1985-02-08 1986-08-15 株式会社日立製作所 Method of treating radioactive waste liquor

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9739545B2 (en) 2009-12-04 2017-08-22 G.M.A. Srl Method for coating a mechanical member, and mechanical member thus coated
CN109830324A (en) * 2019-01-17 2019-05-31 中国辐射防护研究院 A kind of charging feed liquid and preparation method suitable for pyrolytic incineration method processing Radioactive myocardial damage
CN109830324B (en) * 2019-01-17 2022-11-25 中国辐射防护研究院 Feed liquid suitable for treating radioactive organic waste liquid by pyrolysis incineration method and preparation method
CN110975613A (en) * 2019-12-04 2020-04-10 沈阳环境科学研究院 Regeneration method of sodium-alkali desulfurizing agent
CN115105857A (en) * 2021-03-23 2022-09-27 郑州天一萃取科技有限公司 Purifying treatment agent and purifying method for tributyl phosphate waste organic phase

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