Method for collecting uranium by treatment process of washing waste liquid generated in uranium hexafluoride cylinder washing process

Patent metadata

Field	Value
Publication number	US-2022068516-A1
Application number	US-202117524036-A
Country	US
Kind code	A1
Filing date	Nov 11, 2021
Priority date	Apr 28, 2016
Publication date	Mar 3, 2022
Grant date	—

Abstract

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF 6 ) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF 6 ) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF 6 ) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

First claim

1 . A device for recovering uranium (U) using a process for treating a washing wastewater released during a washing process of a uranium hexafluoride (UF 6 ) cylinder, the device comprising:
a NaDU reactor for adding sodium hydroxide (NaOH) to the washing wastewater (hydrogen peroxide (H 2 O 2 )+sodium carbonate (Na 2 CO 3 )+a uranium complex), released during the washing process of the uranium hexafluoride (UF 6 ) cylinder, to thus precipitate a sodium diuranate (NaDU) solid; a filter separator connected to the NaDU reactor to separate the sodium diuranate (NaDU) solid generated in the NaDU reactor and a filtrate; a filtrate reception tank connected to the filter separator to store the filtrate separated using the filter separator; an evaporation vessel connected to the filtrate reception tank to evaporate the filtrate supplied from the filtrate reception tank; a heat exchanger connected to the evaporation vessel to cool a vapor obtained during evaporation using the evaporation vessel, thus condensing the vapor; and a condensate storage tank connected to the heat exchanger to store a condensate.

2 . The device of claim 1 , wherein another filter separator is connected to the evaporation vessel to separate the sodium diuranate (NaDU) solid and the filtrate.

3 . The device of claim 1 , wherein the condensate storage tank includes a first condensate storage tank, for storing a condensate to be released after amounts of radioactivity and fluorine (F) are checked, and a second condensate storage tank, for storing a condensate that is to be chemically treated.

Assignees

• Bae Youngmoon
• Shin Hyundong
• Yang Seungchul
• Jo Bohyun
• Lee Byungkuk
• Kwak Dongyong
• Cho Hyunkwang
• Gu Sunghoi
• Hwang Euijun
• Kepco Nuclear Fuel Co Ltd

Inventors

• Bae Youngmoon
• Shin Hyundong
• Yang Seungchul
• Jo Bohyun
• Lee Byungkuk
• Kwak Dongyong
• Cho Hyunkwang
• Gu Sunghoi
• Hwang Euijun

Classifications

• C22B60/0278 Primary

  by chemical methods (C22B60/0256, C22B60/026, C22B60/0265 take precedence) · CPC title

• C02F2101/006

  Radioactive compounds · CPC title

• C02F11/10

  by pyrolysis · CPC title

• C02F1/52

  by flocculation or precipitation of suspended impurities {(C02F1/463 takes precedence)} · CPC title

• C02F1/66

  by neutralisation; pH adjustment (for degassing C02F1/20; using ion-exchange C02F1/42; for flocculation or precipitation of suspended impurities C02F1/52; for removing dissolved compounds C02F1/58) · CPC title