Method of treatment of radioactive wastewater

Patent metadata

Field	Value
Publication number	US-10046987-B2
Application number	US-201514754745-A
Country	US
Kind code	B2
Filing date	Jun 30, 2015
Priority date	Mar 28, 2013
Publication date	Aug 14, 2018
Grant date	Aug 14, 2018

Abstract

A method of treatment of radioactive wastewater. The method includes: allowing radioactive wastewater to undergo reverse osmosis treatment and continuous electrodeionization treatment in sequence. The continuous electrodeionization treatment is carried out in a continuous electrodeionization unit including a continuous electrodeionization membrane stack including a dilute chamber and a concentrate chamber. The dilute chamber is filled with between 30 and 60 vol. % of a first strong-acid cation exchange resin, between 40 and 60 vol. % of a first strong-base anion exchange resin, and between 0 and 30 vol. % of a weak-base anion exchange resin. The concentrate chamber is filled with between 20 and 50 vol. % of a second strong-acid cation exchange resin, and the rest is a second strong-base anion exchange resin.

First claim

The invention claimed is:

1. A method of treatment of radioactive wastewater, the method comprising:
1) treating the radioactive wastewater by primary reverse osmosis to yield a first permeate and a first concentrate;
2) when an electrical conductivity of the first permeate is larger than 300 μS/cm, treating the first permeate by secondary reverse osmosis to yield a second permeate and a second concentrate;
3) when the electrical conductivity of the first permeate is smaller than or equal to 300 μS/cm, treating the first permeate in a continuous electrodeionization unit, or when the electrical conductivity of the first permeate is larger than 300 μS/cm, treating the second permeate in the continuous electrodeionization unit, to yield a product and a third concentrate; wherein the continuous electrodeionization unit comprises a continuous electrodeionization membrane stack comprising a dilute-solution chamber and a concentrate chamber; the product is generated in the dilute-solution chamber and the third concentrate is generated in the concentrate chamber; the dilute-solution chamber is filled with between 30 and 40 vol. % of a first strong-acid cation exchange resin, between 50 and 60 vol. % of a first strong-base anion exchange resin, and 10 vol. % of a weak-base anion exchange resin; and the concentrate chamber is filled with a combination of a second strong-acid cation exchange resin and a second strong-base anion exchange resin, and the second strong-acid cation exchange resin occupies between 20 and 50 vol. % of the combination.

2. The method of claim 1 , comprising:
before 1), passing the radioactive wastewater through a cartridge filter or a sand filter to remove particulate matters to obtain a treated radioactive wastewater, and then passing the treated radioactive wastewater through an ultrafiltration unit to remove suspended solids and colloid impurities; and
returning the second concentrate from the secondary reverse osmosis to the primary reverse osmosis; wherein the primary reverse osmosis and the secondary reverse osmosis remove a portion of salts and radionuclides from the radioactive wastewater; and the electrical conductivity of the second permeate is less than or equal to 40 μS/cm.

3. The method of claim 2 , wherein a volume ratio of the first permeate to the first concentrate is between 3:1 and 10:1, a volume ratio of the second permeate to the second concentrate is between 5:1 and 10:1, and microorganisms in the second permeate are in a concentration of less than or equal to 200 CFU/mL.

4. The method of claim 2 , wherein a volume ratio of the product to the third concentrate is between 3:1 and 5:1.

5. The method of claim 2 , further comprising:
4) concentrating the first concentrate to yield a dilute solution and a concentrate solution, and returning the dilute solution and the third concentrate to the primary reverse osmosis for further treatment; and
5) mixing and stirring the concentrate solution obtained in 4) with cement to yield a solidified waste.

6. The method of claim 5 , wherein in 4), the concentrating of the first concentrate is achieved through membrane distillation or evaporation; and a salinity of the concentrate solution is less than or equal to 200 g/L.

Assignees

• Univ Tsinghua

Inventors

• Zhao Xuan
• Li Fuzhi
• Zhang Meng

Classifications

• Y02A20/131

  Reverse-osmosis · CPC title

• C02F2101/006

  Radioactive compounds · CPC title

• C02F1/441 Primary

  by reverse osmosis · CPC title

• G21F9/06

  Processing (separating different isotopes of the same chemical element B01D59/00) · CPC title

• C02F1/4695

  electrodeionisation · CPC title