CN102915783A - Flocculation adsorption treatment method of waste liquid of nuclear power plant and flocculating agent - Google Patents

Flocculation adsorption treatment method of waste liquid of nuclear power plant and flocculating agent Download PDF

Info

Publication number
CN102915783A
CN102915783A CN2012104100245A CN201210410024A CN102915783A CN 102915783 A CN102915783 A CN 102915783A CN 2012104100245 A CN2012104100245 A CN 2012104100245A CN 201210410024 A CN201210410024 A CN 201210410024A CN 102915783 A CN102915783 A CN 102915783A
Authority
CN
China
Prior art keywords
power plant
nuclear power
component
waste liquid
flocculating agent
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.)
Granted
Application number
CN2012104100245A
Other languages
Chinese (zh)
Other versions
CN102915783B (en
Inventor
刘杰安
陈斌
王鑫
柳丹
朱来叶
翁明辉
谈遗海
储志军
刘兵
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.)
JIANGSU BAOCHEN PURIFYING EQUIPMENT CO Ltd
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Original Assignee
JIANGSU BAOCHEN PURIFICATION EQUIPMENT CO Ltd
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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 JIANGSU BAOCHEN PURIFICATION EQUIPMENT CO Ltd, Shanghai Nuclear Engineering Research and Design Institute Co Ltd filed Critical JIANGSU BAOCHEN PURIFICATION EQUIPMENT CO Ltd
Priority to CN201210410024.5A priority Critical patent/CN102915783B/en
Publication of CN102915783A publication Critical patent/CN102915783A/en
Application granted granted Critical
Publication of CN102915783B publication Critical patent/CN102915783B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Abstract

The invention provides a flocculation adsorption treatment method of waste liquid of a nuclear power plant and a flocculating agent. The flocculation adsorption treatment method includes the steps of adding flocculating agent into the waste liquid of the nuclear power plant, keeping a pH (potential of hydrogen) value within 7-9, performing mixed reaction to obtain colloid flocculation; and subjecting the colloid flocculation to activated carbon adsorption column for adsorption, wherein Fe, Co, Mn and Ag nuclides are absorbed and intercepted by the activated carbon adsorption column. The flocculating agent comprises a component A including NaOH or KOH, a component B which is polyacrylamide, a component C which is sodium polyacrylate or potassium polyacrylate. Coagulation capacity of corrosion product colloids is improved by adding the flocculating agent, and decontamination factor of activated carbon to Fe, Co, Mn, Ag is increased by 5 times. The flocculation adsorption treatment method is stable in eliminating effect, good in repeatability, low in running energy consumption and less in secondary pollution output.

Description

Flocculation adsorption treatment method and the flocculating agent of a kind of nuclear power plant waste liquid
Technical field
The present invention relates to nuclear power plant's liquid waste disposal technique, particularly relate to flocculation adsorption treatment method and the flocculating agent of a kind of nuclear power plant waste liquid.
Background technology
Nuclear power plant's operation inevitably produces radioactive liquid waste.Along with the development of China's nuclear power, nuclear power plant construction more and more receives publicity on the impact of water environment.In order to protect the environmental radiation of new period China's Construction of Nuclear Electricity and impact, provide safer, reasonable, effectively, value disciplines accurately, the national environmental protection section a collection of new liter (10-3Li Fangmi) version nuclear power waste discharge administrative standard take " regulation of protection of GB 6249-2011 nuclear power plant environmental radiation " as representative of having taken the lead in official approval in 2011.Standard code Coastal Nuclear Power Plant (detritiation and C14 are outer) liquid radiation effluent total radioactivity concentration limit value is decided to be 1000Bq/L, and this concentration limit of landlocked nuclear power plant then is decided to be 100Bq/L.
It is pressurized water reactor type that the existing operation of China reaches building nuclear power plant most.For PWR nuclear power plant, the source of radioactive liquid waste mainly contains chemical waste fluid, process waste liquor, miscellaneous waste liquid, scrub raffinate and potential radioactive liquid waste.Wherein the process waste liquor activity concentration is the highest, can reach 107Bq/L.Process waste liquor mainly comprises the reactor coolant efflux, comprises also that equipment is hydrophobic, refuelling pool and spentnuclear fuel pond are hydrophobic etc.Its contained liquid radiomaterial mainly comprises the corrosion product that fission product that Cs, Sr etc. exist with ionic forms and Co, Mn etc. exist with colloid, particle shape.
The disposal route of radioactive liquid waste mainly contains chemical precipitation, evaporation, ion-exchange, film processing, chemical flocculation, charcoal absorption, continuous electric desalination etc. at present.
Chemical precipitation is widely used in the processing of early stage nuclear facilities radioactive liquid waste, but the decontamination factor that chemical precipitation is processed is lower, equipment is huge and need more chemical reagent, secondary refuse generation large, when processing nuclear power plant's waste liquid, generally only be used as pre-service at present.
In the nuclear power plant that China has moved at present, liquid waste system has nearly all adopted evaporation treatment process, do not contain waste liquid easy to foaming, volatile component but evaporation treatment process is suitable for processing, and operation energy consumption is high, maintenance, repair are complicated, and concentrate also needs further to process or dispose.
Ion-exchange is the most frequently used treatment process of nuclear power plant's active-effluent system, many ion exchange beds series connection of general employing (or in parallel) operation, do not process salt content or the higher waste liquid of solid content but resin bed is suitable for: when salinity was more in the waste liquid, resin will soon saturatedly lose efficacy; When solid content was higher in the waste liquid, resin bed caused runner to stop up easily.
Membrane technology provides new selection for the processing of radioactive liquid waste, but film processes and to have certain shortcoming, still needs further to process, the concentrate that produces limited, high to maintenance requirement such as: detergent power etc.Wherein the most frequently used reverse-osmosis treated is had relatively high expectations to influent quality, and the upstream of reverse-osmosis treated need adopt filtration etc. that waste liquid is carried out pre-service.
At present, radioactive liquid waste is processed and is also developed many advanced persons' treatment process, comprising: adopt novel sorbing material to adsorb, continuous electric desalination, electrochemical ion exchange etc.But these treatment technologies seldom are applied to the processing of radioactive liquid waste in the nuclear power plant also in conceptual phase.
Summary of the invention
In order to overcome above-mentioned the deficiencies in the prior art, satisfy simultaneously the emission limit requirement of GB 6249-2011 new standard, the invention provides flocculation adsorption treatment method and the flocculating agent of a kind of nuclear power plant waste liquid.
Realize the technical scheme of the object of the invention: the flocculation adsorption treatment method of a kind of nuclear power plant waste liquid, it comprises the steps:
(1) add flocculating agent in nuclear power plant's waste liquid, every liter of nuclear power plant's waste liquid adds flocculating agent 1.1mg ~ 14.2mg, makes the pH value remain on 7 ~ 9, and hybrid reaction obtains the colloid flco;
Described nuclear power plant waste liquid comprises one or more in Fe, Co, Mn, the Ag corrosion product; Wherein, Fe, Co, Mn or Ag nuclide concentration are at 0.01ng/L ~ 10mg/L;
Described flocculating agent comprises following component; A component: NaOH or KOH; B component: polyacrylamide; C component: sodium polyacrylate or polyacrylic acid potassium; Wherein, A component, B component are (0.1 ~ 12.3): 1:(0.5 ~ 2 with C constituent mass ratio);
(2) the colloid flco with step (1) gained passes through active carbon adsorption column, and wherein Fe, Co, Mn, Ag nucleic are held back by active carbon adsorption column absorption; Described activated carbon granule is of a size of 20 ~ 50 orders, and the iodine number is 〉=900mg/g.
The colloid flco passes through active carbon adsorption column with the flow velocity of 10m/h~25m/h in the chemical flocculation disposal route of aforesaid a kind of nuclear power plant waste liquid, its described step (2).
The chemical flocculation disposal route of aforesaid a kind of nuclear power plant waste liquid, its described active carbon adsorption column loading height is 0.2m ~ 0.85m.
The chemical flocculation disposal route of aforesaid a kind of nuclear power plant waste liquid, the average decontamination factor of Fe, Co, Mn, Ag nucleic colloid reaches more than 50 in the last gained waste liquid of its step (2).
The chemical flocculation disposal route of aforesaid a kind of nuclear power plant waste liquid, its described polyacrylamide is cationic, its solid content 〉=90%, molecular weight 〉=3 * 10 6
The chemical flocculation disposal route of aforesaid a kind of nuclear power plant waste liquid, the solid content of its described sodium polyacrylate 〉=40%, molecular weight 〉=3 * 10 7
A kind of flocculating agent for nuclear power plant's liquid waste processing of the present invention, it is the aqueous solution that comprises following component; A component: NaOH or KOH; B component: polyacrylamide; C component: sodium polyacrylate or polyacrylic acid potassium; Wherein, the mass concentration ratio of A component, B component and C component is (0.1 ~ 12.3): 1:(0.5 ~ 2).
Aforesaid a kind of flocculating agent for nuclear power plant's liquid waste processing, its described polyacrylamide is cationic, its solid content 〉=90%, molecular weight 〉=3 * 10 6
Aforesaid a kind of flocculating agent for nuclear power plant's liquid waste processing, the solid content of its described sodium polyacrylate 〉=40%, molecular weight 〉=3 * 10 7
Effect of the present invention is:
(1) traditional flocculation precipitation method is for the higher liquid waste processing of salt content, and decontamination factor lower (usually about 10).The flocculation adsorption method that the present invention proposes is applicable to nuclear power plant's low concentration liquid waste processing, but the dirt-removing power of Effective Raise nuclear power plant liquid waste system has significant effect (average decontamination factor reaches more than 50) for Fe, Co, Mn, Ag with the removal of the corrosion product that colloidal form exists.
(2) than the charcoal absorption method, the flocculation adsorption method that the present invention proposes improves the coagulation ability of corrosion product colloid by adding flocculating agent, makes activated charcoal improve more than 5 times to the decontamination factor of Fe, Co, Mn, Ag.
(3) the flocculation adsorption method removal effect of the present invention's proposition is stable, favorable reproducibility, and operation energy consumption is low, and secondary refuse generation is few.
(4) the flocculating agent safety and environmental protection of the present invention's proposition, the preparation method is simple, and cost economy has popularizing application prospect in nuclear power plant liquid waste processing field.
Embodiment
Be described in further detail below in conjunction with flocculation adsorption treatment method and the flocculating agent of specific embodiment to a kind of nuclear power plant of the present invention waste liquid.
Embodiment 1
(1) add flocculating agent in nuclear power plant's waste liquid, every liter of nuclear power plant's waste liquid adds flocculating agent 12.4mg, makes the pH value remain on 9, and hybrid reaction 15s obtains the colloid flco;
Described nuclear power plant waste liquid comprises 4.5mg/L Fe, 7.2mg/L Co, 1.8mg/L Mn;
Described flocculating agent comprises following component; A component: NaOH; B component: polyacrylamide; C component: sodium polyacrylate; Wherein, A component, B component are 1.1:1:1 with C constituent mass ratio;
(2) the colloid flco of step (1) gained is passed through active carbon adsorption column with the flow velocity of 20m/h, wherein flco is held back by active carbon adsorption column absorption, the decontamination factor of Fe, Co, Mn nucleic colloid is respectively in the gained waste liquid: 150,82,67, and average decontamination factor is 93;
Described active carbon adsorption column loading height is 0.2m; Described activated carbon granule is of a size of the 20-50 order, and the iodine number is 〉=900mg/g.
Embodiment 2
(1) add flocculating agent in nuclear power plant's waste liquid, every liter of nuclear power plant's waste liquid adds flocculating agent 10mg, makes the pH value remain on 7, and hybrid reaction 15s obtains the colloid flco;
Described nuclear power plant waste liquid comprises 3.1mg/L Fe, 4.4mg/L Co, 1.1mg/L Mn;
Described flocculating agent comprises following component; A component: NaOH; B component: polyacrylamide; C component: sodium polyacrylate; Wherein, A component, B component are 8:1:1 with C constituent mass ratio;
(2) the colloid flco of step (1) gained is passed through active carbon adsorption column with the flow velocity of 10m/h, wherein flco is held back by active carbon adsorption column absorption, the decontamination factor of Fe, Co, Mn nucleic colloid is respectively in the gained waste liquid: 104,102,16, and comprehensive decontamination factor is 61;
Described active carbon adsorption column loading height is 0.85m; Described activated carbon granule is of a size of the 20-50 order, and the iodine number is 〉=900mg/g.
Embodiment 3
(1) add flocculating agent in nuclear power plant's waste liquid, every liter of nuclear power plant's waste liquid adds flocculating agent 8.4mg, makes the pH value remain on 9, and hybrid reaction 15s obtains the colloid flco;
Described nuclear power plant waste liquid comprises 1.5mg/LAg;
Described flocculating agent comprises following component; A component: NaOH; B component: polyacrylamide; C component: sodium polyacrylate; Wherein, A component, B component are 2.2:1:1 with C constituent mass ratio;
(2) with the colloid flco of step (1) gained with the flow velocity of 20m/h by active carbon adsorption column, wherein flco is held back by active carbon adsorption column absorption, the decontamination factor of Ag nucleic colloid is 91 in the gained waste liquid;
Described active carbon adsorption column loading height is 0.2m; Described activated carbon granule is of a size of the 20-50 order, and the iodine number is 〉=900mg/g.
Embodiment 4
(1) add flocculating agent in nuclear power plant's waste liquid, every liter of nuclear power plant's waste liquid adds flocculating agent 14.2mg, makes the pH value remain on 9, and hybrid reaction 15s obtains the colloid flco;
Described nuclear power plant waste liquid comprises 3.1mg/L Fe, 4.0mg/L Co, 1.0mg/L Mn;
Described flocculating agent comprises following component; A component: KOH; B component: polyacrylamide; C component: polyacrylic acid potassium; Wherein, A component, B component are 1.55:1:1 with C constituent mass ratio;
(2) the colloid flco of step (1) gained is passed through active carbon adsorption column with the flow velocity of 25m/h, wherein flco is held back by active carbon adsorption column absorption, the decontamination factor of Fe, Co, Mn nucleic colloid is respectively in the gained waste liquid: 102,85,101, and average decontamination factor is 93;
Described active carbon adsorption column loading height is 0.2m; Described activated carbon granule is of a size of the 20-50 order, and the iodine number is 〉=900mg/g.
Embodiment 5
(1) add flocculating agent in nuclear power plant's waste liquid, every liter of nuclear power plant's waste liquid adds flocculating agent 7.65mg, makes the pH value remain on 9, and hybrid reaction 15s obtains the colloid flco;
Described nuclear power plant waste liquid comprises 3.1mg/L Fe, 4.0mg/L Co, 1.0mg/L Mn;
Described flocculating agent comprises following component; A component: KOH; B component: polyacrylamide; C component: sodium polyacrylate; Wherein, A component, B component are 12.3:1:2 with C constituent mass ratio;
(2) the colloid flco of step (1) gained is passed through active carbon adsorption column with the flow velocity of 20m/h, wherein flco is held back by active carbon adsorption column absorption, the decontamination factor of Fe, Co, Mn nucleic colloid is respectively in the gained waste liquid: 102,60,90, and average decontamination factor is 75;
Described active carbon adsorption column loading height is 0.2m; Described activated carbon granule is of a size of the 20-50 order, and the iodine number is 〉=900mg/g.
Embodiment 6
(1) add flocculating agent in nuclear power plant's waste liquid, every liter of nuclear power plant's waste liquid adds flocculating agent 6.4mg, makes the pH value remain on 7, and hybrid reaction 15s obtains the colloid flco;
Described nuclear power plant waste liquid comprises 4.4mg/L Fe, 6.4mg/L Co, 1.7mg/L Mn;
Described flocculating agent comprises following component; A component: NaOH; B component: polyacrylamide; C component: sodium polyacrylate; Wherein, A component, B component are 0.1:1:0.5 with C constituent mass ratio;
(2) the colloid flco of step (1) gained is passed through active carbon adsorption column with the flow velocity of 20m/h, wherein flco is held back by active carbon adsorption column absorption, the decontamination factor of Fe, Co, Mn nucleic colloid is respectively in the gained waste liquid: 55,49,56, and comprehensive decontamination factor is 52;
Described active carbon adsorption column loading height is 0.2m; Described activated carbon granule is of a size of the 20-50 order, and the iodine number is 〉=900mg/g.

Claims (9)

1. the flocculation adsorption treatment method of nuclear power plant's waste liquid, it is characterized in that: the method comprises the steps:
(1) add flocculating agent in nuclear power plant's waste liquid, every liter of nuclear power plant's waste liquid adds flocculating agent 1.1mg ~ 14.2mg, makes the pH value remain on 7 ~ 9, and hybrid reaction obtains the colloid flco;
Described nuclear power plant waste liquid comprises one or more in Fe, Co, Mn, the Ag corrosion product; Wherein, Fe, Co, Mn or Ag nuclide concentration are at 0.01ng/L ~ 10mg/L;
Described flocculating agent comprises following component; A component: NaOH or KOH; B component: polyacrylamide; C component: sodium polyacrylate or polyacrylic acid potassium; Wherein, A component, B component are (0.1 ~ 12.3): 1:(0.5 ~ 2 with C constituent mass ratio);
(2) the colloid flco with step (1) gained passes through active carbon adsorption column, and wherein Fe, Co, Mn, Ag nucleic are held back by active carbon adsorption column absorption; Described activated carbon granule is of a size of 20 ~ 50 orders, and the iodine number is 〉=900mg/g.
2. the chemical flocculation disposal route of a kind of nuclear power plant according to claim 1 waste liquid, it is characterized in that: the colloid flco passes through active carbon adsorption column with the flow velocity of 10m/h~25m/h in the described step (2).
3. the chemical flocculation disposal route of a kind of nuclear power plant according to claim 1 and 2 waste liquid, it is characterized in that: described active carbon adsorption column loading height is 0.2m ~ 0.85m.
4. the chemical flocculation disposal route of a kind of nuclear power plant according to claim 1 waste liquid, it is characterized in that: the average decontamination factor of Fe, Co, Mn, Ag nucleic colloid reaches more than 50 in the last gained waste liquid of step (2).
5. the chemical flocculation disposal route of a kind of nuclear power plant according to claim 1 waste liquid, it is characterized in that: described polyacrylamide is cationic, its solid content 〉=90%, molecular weight 〉=3 * 10 6
6. the chemical flocculation disposal route of a kind of nuclear power plant according to claim 1 waste liquid is characterized in that: the solid content of described sodium polyacrylate 〉=40%, molecular weight 〉=3 * 10 7
7. flocculating agent that is used for nuclear power plant's liquid waste processing, it is characterized in that: this flocculating agent is the aqueous solution that comprises following component;
A component: NaOH or KOH;
B component: polyacrylamide;
C component: sodium polyacrylate or polyacrylic acid potassium;
Wherein, the mass concentration ratio of A component, B component and C component is (0.1 ~ 12.3): 1:(0.5 ~ 2).
8. a kind of flocculating agent for nuclear power plant's liquid waste processing according to claim 7, it is characterized in that: described polyacrylamide is cationic, its solid content 〉=90%, molecular weight 〉=3 * 10 6
9. a kind of flocculating agent for nuclear power plant's liquid waste processing according to claim 7 is characterized in that: the solid content of described sodium polyacrylate 〉=40%, molecular weight 〉=3 * 10 7
CN201210410024.5A 2012-10-24 2012-10-24 Flocculation adsorption treatment method of waste liquid of nuclear power plant and flocculating agent Active CN102915783B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201210410024.5A CN102915783B (en) 2012-10-24 2012-10-24 Flocculation adsorption treatment method of waste liquid of nuclear power plant and flocculating agent

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201210410024.5A CN102915783B (en) 2012-10-24 2012-10-24 Flocculation adsorption treatment method of waste liquid of nuclear power plant and flocculating agent

Publications (2)

Publication Number Publication Date
CN102915783A true CN102915783A (en) 2013-02-06
CN102915783B CN102915783B (en) 2015-06-03

Family

ID=47614115

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201210410024.5A Active CN102915783B (en) 2012-10-24 2012-10-24 Flocculation adsorption treatment method of waste liquid of nuclear power plant and flocculating agent

Country Status (1)

Country Link
CN (1) CN102915783B (en)

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103714875A (en) * 2013-12-30 2014-04-09 中国原子能科学研究院 Device for removing Ag gel in nuclear waste water
WO2014153965A1 (en) * 2013-03-28 2014-10-02 南京大学宜兴环保研究院 Composite flocculating agent and method for processing radioactive elements iron, cobalt, manganese and silver in nuclear wastewater
CN104538077A (en) * 2013-12-06 2015-04-22 东华理工大学 Method for treating acidic uranium-bearing wastewater with bone-based adsorbent
CN104867528A (en) * 2015-03-31 2015-08-26 湖南桃花江核电有限公司 Treatment method of process wastewater in nuclear power plant
CN107140721A (en) * 2017-04-21 2017-09-08 中铁四局集团有限公司 A kind of discarded slurry mud-water separation preparation and its application process
CN109493988A (en) * 2018-12-14 2019-03-19 核工业理化工程研究院 Core biochemical decontamination waste liquid pretreatment unit and processing method
CN110467179A (en) * 2018-05-09 2019-11-19 上海核工程研究设计院有限公司 A method of active carbon is handled with nuclear facilities radioactive liquid waste chemical flocculation
CN112970764A (en) * 2021-04-21 2021-06-18 北京科奥明生物技术有限公司 Microbial waste liquid treatment agent and microbial waste liquid treatment bag

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006010424A (en) * 2004-06-24 2006-01-12 Ishikawajima Harima Heavy Ind Co Ltd Uranium recovery facility and uranium recovery method
CN101289260A (en) * 2008-05-28 2008-10-22 侯玉奇 System and method for treating fluorine-containing acid wastewater after graphite purification
WO2010049396A1 (en) * 2008-10-27 2010-05-06 Commissariat A L'energie Atomique Method for decontaminating a liquid effluent containing one or more radioactive chemical elements by a fluidised bed treatment
CN102139974A (en) * 2011-02-21 2011-08-03 李开明 Treatment method of phosphorus-containing waste water

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2006010424A (en) * 2004-06-24 2006-01-12 Ishikawajima Harima Heavy Ind Co Ltd Uranium recovery facility and uranium recovery method
CN101289260A (en) * 2008-05-28 2008-10-22 侯玉奇 System and method for treating fluorine-containing acid wastewater after graphite purification
WO2010049396A1 (en) * 2008-10-27 2010-05-06 Commissariat A L'energie Atomique Method for decontaminating a liquid effluent containing one or more radioactive chemical elements by a fluidised bed treatment
CN102139974A (en) * 2011-02-21 2011-08-03 李开明 Treatment method of phosphorus-containing waste water

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2014153965A1 (en) * 2013-03-28 2014-10-02 南京大学宜兴环保研究院 Composite flocculating agent and method for processing radioactive elements iron, cobalt, manganese and silver in nuclear wastewater
CN104538077A (en) * 2013-12-06 2015-04-22 东华理工大学 Method for treating acidic uranium-bearing wastewater with bone-based adsorbent
CN103714875A (en) * 2013-12-30 2014-04-09 中国原子能科学研究院 Device for removing Ag gel in nuclear waste water
CN103714875B (en) * 2013-12-30 2016-06-22 中国原子能科学研究院 Ag colloid removal device in a kind of nuclear waste water
CN104867528A (en) * 2015-03-31 2015-08-26 湖南桃花江核电有限公司 Treatment method of process wastewater in nuclear power plant
CN107140721A (en) * 2017-04-21 2017-09-08 中铁四局集团有限公司 A kind of discarded slurry mud-water separation preparation and its application process
CN110467179A (en) * 2018-05-09 2019-11-19 上海核工程研究设计院有限公司 A method of active carbon is handled with nuclear facilities radioactive liquid waste chemical flocculation
CN109493988A (en) * 2018-12-14 2019-03-19 核工业理化工程研究院 Core biochemical decontamination waste liquid pretreatment unit and processing method
CN112970764A (en) * 2021-04-21 2021-06-18 北京科奥明生物技术有限公司 Microbial waste liquid treatment agent and microbial waste liquid treatment bag

Also Published As

Publication number Publication date
CN102915783B (en) 2015-06-03

Similar Documents

Publication Publication Date Title
CN102915783B (en) Flocculation adsorption treatment method of waste liquid of nuclear power plant and flocculating agent
CN103480328A (en) Composite adsorbing agent for separating radioactive cesium and preparation method thereof
US20090296873A1 (en) Method and apparatus for condensate demineralization
Khamis et al. IAEA coordinated research activity on nuclear desalination: the quest for new technologies and techno-economic assessment
CN105645624A (en) Resource utilization method for high-salt wastewater from epichlorohydrin preparation through glycerol method
Hafeez et al. Fenton-like treatment for reduction of simulated carbon-14 spent resin
CN102603050B (en) Method for preprocessing nitrobenzene-contained waste water by ferrous sulfide
Liu et al. The latest research trends in the removal of cesium from radioactive wastewater: A review based on data-driven and visual analysis
Qin et al. Investigation on the by-pass line orifice plate assisted hydrodynamic cavitation (B-PLOPA HC) degradation of basic fuchsin (BF) in wastewater
CN103366850B (en) A kind of method of Wet Catalytic Oxidation Method process radioactivity anion exchange resins
CN102247808A (en) Separating material for separating and extracting technetium from acid solution system
CN103474123B (en) A kind of nanometer Fe/Mn composite catalyst is used for the method for radioactive spent resin oxygenolysis
Rodrigues Silva et al. Uranium biosorption under dynamic conditions: Preliminary tests with Sargassum filipendula in real radioactive wastewater containing Ba, Cr, Fe, Mn, Pb, Ca and Mg
CN104575652B (en) The treating method and apparatus of nuclear spent fuel pond water purification method and device and spentnuclear fuel water
Narbutt et al. Studies on new titanium hexacyanoferrate sorbents for radiocesium removal from primary coolant of pressurized water reactors
NL2029939B1 (en) Treatment process for purifying chlorine-containing wastewater by crystallization of ammonium salt
JP5038232B2 (en) Condensate demineralization method and condensate demineralization apparatus
CN209333534U (en) A kind of ultra-low-pressure reverse osmosis system
Park et al. A study on adsorption and desorption behaviors of 14C from a mixed bed resin
CN106277543B (en) Cities and towns drinking water mineral spring handling process
CN103714875B (en) Ag colloid removal device in a kind of nuclear waste water
Matskevich et al. Decontamination of spent ion-exchange resins from the nuclear fuel cycle using chemical decontamination and direct current
Choi et al. 14C removal technology for the treatment of spent resin from nuclear power plants: a review
Vinnitskii et al. Prospects for using weakly dissociated ion exchange resins in special water treatment systems at VVER-based nuclear power plants for reducing the volume of radioactive waste generated
Narbutt et al. Composite Ion Exchangers for Radiocaesium Removal from Nuclear Reactor Wastes

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant
CP01 Change in the name or title of a patent holder

Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.

Patentee after: JIANGSU BAOCHEN PURIFYING EQUIPMENT CO.,LTD.

Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd.

Patentee before: JIANGSU BAOCHEN PURIFYING EQUIPMENT CO.,LTD.

Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd.

Patentee after: JIANGSU BAOCHEN PURIFYING EQUIPMENT CO.,LTD.

Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE

Patentee before: JIANGSU BAOCHEN PURIFYING EQUIPMENT CO.,LTD.

CP01 Change in the name or title of a patent holder