JPS6463900A - Treatment of radioactive waste liquid containing sodium sulfate - Google Patents

Treatment of radioactive waste liquid containing sodium sulfate

Info

Publication number
JPS6463900A
JPS6463900A JP22069487A JP22069487A JPS6463900A JP S6463900 A JPS6463900 A JP S6463900A JP 22069487 A JP22069487 A JP 22069487A JP 22069487 A JP22069487 A JP 22069487A JP S6463900 A JPS6463900 A JP S6463900A
Authority
JP
Japan
Prior art keywords
sodium sulfate
waste liquid
radioactive waste
treatment
containing sodium
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
JP22069487A
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 JP22069487A priority Critical patent/JPS6463900A/en
Publication of JPS6463900A publication Critical patent/JPS6463900A/en
Pending legal-status Critical Current

Links

Abstract

PURPOSE:To considerably reduce volume without using heating material by taking out radioactive waste liquid containing sodium sulfate as solidified materials of calcium sulfate containing radioactive substances. CONSTITUTION:Calcium oxide (CaO) or calcium hydroxide (Ca(OH2)) is added, mixed and agitated in radioactive waste liquid containing sodium sulfate produced in a nuclear power plant. Heating treatment is performed, and solid and liquid are separated from each other if necessary. Solid deposited substances after solid and liquid are separated from each other is calcium sulfate (CaSO4) in which the greater part of radiated materials such as Fe, Cr, Co, Mn is included, and kept as it is or forming material is mixed to solidify as after-treatment, heated and made into anhydrous salt and solidified so as to adsorb water. The liquid is sodium hydroxide (NaOH) solution to use again or used to separate alkali metal such as Cs. Therefore, the danger of a fire is eliminated, the volume of production of solidified materials can be reduced and economical efficiency can also be improved.
JP22069487A 1987-09-03 1987-09-03 Treatment of radioactive waste liquid containing sodium sulfate Pending JPS6463900A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP22069487A JPS6463900A (en) 1987-09-03 1987-09-03 Treatment of radioactive waste liquid containing sodium sulfate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP22069487A JPS6463900A (en) 1987-09-03 1987-09-03 Treatment of radioactive waste liquid containing sodium sulfate

Publications (1)

Publication Number Publication Date
JPS6463900A true JPS6463900A (en) 1989-03-09

Family

ID=16755026

Family Applications (1)

Application Number Title Priority Date Filing Date
JP22069487A Pending JPS6463900A (en) 1987-09-03 1987-09-03 Treatment of radioactive waste liquid containing sodium sulfate

Country Status (1)

Country Link
JP (1) JPS6463900A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111226293A (en) * 2017-04-12 2020-06-02 原子能股份公司 Method for controlling and treating waste liquid of nuclear power station by using boron

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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 (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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 (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111226293A (en) * 2017-04-12 2020-06-02 原子能股份公司 Method for controlling and treating waste liquid of nuclear power station by using boron
JP2020516850A (en) * 2017-04-12 2020-06-11 ジョイント ストック カンパニー“ロスエネルゴアトム” Recycling method of liquid nuclear waste by controlling boron concentration
CN111226293B (en) * 2017-04-12 2023-09-01 原子能股份公司 Method for controlling and treating nuclear power station waste liquid by using boron

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