CN107658038A - Radiological techniques treatment of wastes produced method - Google Patents

Radiological techniques treatment of wastes produced method Download PDF

Info

Publication number
CN107658038A
CN107658038A CN201710762191.9A CN201710762191A CN107658038A CN 107658038 A CN107658038 A CN 107658038A CN 201710762191 A CN201710762191 A CN 201710762191A CN 107658038 A CN107658038 A CN 107658038A
Authority
CN
China
Prior art keywords
pva
treatment
wastes produced
radiological techniques
produced method
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
CN201710762191.9A
Other languages
Chinese (zh)
Other versions
CN107658038B (en
Inventor
邓才远
张惠炜
蒲江
赵滢
何小平
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.)
China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
Original Assignee
China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power 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 China General Nuclear Power Corp, CGN Power Co Ltd, Daya Bay Nuclear Power Operations and Management Co Ltd, Lingdong Nuclear Power Co Ltd, Guangdong Nuclear Power Joint Venture Co Ltd, Lingao Nuclear Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN201710762191.9A priority Critical patent/CN107658038B/en
Publication of CN107658038A publication Critical patent/CN107658038A/en
Application granted granted Critical
Publication of CN107658038B publication Critical patent/CN107658038B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Treatment Of Water By Oxidation Or Reduction (AREA)
  • Catalysts (AREA)

Abstract

The present invention provides a kind of radiological techniques treatment of wastes produced method.The processing method comprises at least following steps：By contact agent dose rate in surface caused by nuclear power plant<2mSv/h PVA product waste materials, which are placed in water, to be heated, and is dissolved PVA product waste materials, is obtained the PVA aqueous solution；Fenton reagent is added into the PVA aqueous solution, makes PVA that oxidative degradation occur, obtains degradation solution；Degradation solution is subjected to filtration treatment, filters out the insoluble matter that particle diameter is more than 0.25 μm, and heated oxide processing is carried out to filtrate, makes activity concentration≤1MBq/m of filtrate3, COD≤100mg/L；BOD≤30mg, collects the gas of heated oxide processing discharge, and catalytic oxidation treatment is carried out to gas.Treatment method technique is simple, less energy consumption, is advantageous to energy-saving and emission-reduction and environmental protection, avoids the accumulation of PVA products waste material in nuclear power plant, and obtained product is environmentally friendly.

Description

Radiological techniques treatment of wastes produced method
Technical field
The invention belongs to nuclear pollution waste processing arts, and in particular to a kind of radiological techniques treatment of wastes produced side Method.
Background technology
As nuclear technology utilizes, the fast development of nuclear power station, nuclear power plant generates largely during operation and refueling outage Technology waste.These technology wastes mainly apply maintenance protective articles, such as plastic cloth/bag plastic products.According to original Design these technology wastes and all individually carry out barrelling compression, increase solid waste volume and cost of disposal.Consider from waste minimization, this The processing incineration technology of a little radwastes is maximally efficient, but domestic at present in fortune nuclear power plant introduction incineration technology and its difficulty.
The control zone plastic products in current each nuclear power base use PE products, under the superpressure handling process in power station, deposit In compression rebound effect, larger restriction for existing handling process be present, even if using superpressure technique, volume reduction ratio is also only 30%.And the volume reduction ratio of PVA products can reach 10000:1, therefore PVA products are used to that in nuclear power plant nuclear power can be efficiently reduced The accumulation of solid radioactive technology waste and disposal quantity in factory's running, this make it that PVA is attractive as one Realize the practical technique that radwaste minimizes.In IAEA public publications《IAEA-WMDB-ST-3》6.1 chapters and sections in, EPRI (American Electric Power research association) recommends to realize the volume reduction of solid radioactive waste using PVA materials in nuclear power field.That Accordingly, it is desirable to propose a kind of PVA biodegrading process discarded suitable for nuclear power plant.
The content of the invention
It is more and more for shielding waste material caused by current nuclear power plant, and because can not be according to conventional side with radioactivity The problems such as method processing, the invention provides a kind of radiological techniques treatment of wastes produced method.
In order to realize foregoing invention purpose, the technical scheme of the embodiment of the present invention is as follows：
A kind of radiological techniques treatment of wastes produced method, including at least following steps：
By contact agent dose rate in surface caused by nuclear power plant<2mSv/h PVA product waste materials, which are placed in water, to be heated, PVA product waste materials are hydrolyzed, obtain the PVA aqueous solution；
Fenton reagent is added into the PVA aqueous solution, makes PVA that oxidative degradation occur, obtains degradation solution；
The degradation solution is subjected to filtration treatment, particle diameter is filtered out and is more than 0.25 μm of insoluble matter, and filtrate is heated Oxidation processes, make activity concentration≤1MBq/m of the filtrate3, discharge standard and COD≤100mg/L, BOD≤ 30mg；The gas of the heated oxide processing discharge is collected, catalytic oxidation treatment is carried out to the gas.
Relative to prior art, radiological techniques treatment of wastes produced method provided by the invention, specifically to PVA shieldings Handled, realize surface contact agent dose rate<The degraded of 2mSv/h PVA product waste materials, avoid the heap of PVA product waste materials Product, and catabolite is environmentally friendly, waste liquid activity concentration reaches discharging standards；COD and BOD values reach state Family's discharge mark；The biodegrading process technique is simple, less energy consumption, is advantageous to energy-saving and emission-reduction and environmental protection.
Embodiment
In order to make the purpose , technical scheme and advantage of the present invention be clearer, with reference to embodiments, to the present invention It is further elaborated.It should be appreciated that the specific embodiments described herein are merely illustrative of the present invention, it is not used to Limit the present invention.
Present example provides a kind of radiological techniques treatment of wastes produced method.The processing method comprises at least following step Suddenly：
By contact agent dose rate in surface caused by nuclear power plant<2mSv/h PVA product waste materials, which are placed in water, to be heated, PVA product waste materials are hydrolyzed, obtain the PVA aqueous solution；
Fenton reagent is added into the PVA aqueous solution, makes PVA that oxidative degradation occur, obtains degradation solution；
The degradation solution is subjected to filtration treatment, particle diameter is filtered out and is more than 0.25 μm of insoluble matter, and filtrate is heated Oxidation processes, make activity concentration≤1MBq/m of the filtrate3, COD≤100mg/L, BOD≤30mg；Described in collection The gas of heated oxide processing discharge, catalytic oxidation treatment is carried out to the gas.
Explanation is further explained to the biodegrading process below.
Using the above-mentioned radiological techniques waste treatment method of the present invention to being to caused by nuclear power plant at PVA wastes Reason, PVA products waste material should be met without the nuclear power plants such as halogen, sulfate radical disabling chemical composition.
Carry out before processing, PVA product waste materials should be sorted, it is impossible to degraded and surface contact agent dose rate >= 2mSv/h sorting is removed, because as surface contact agent dose rate >=2mSv/h, discharging standards can not be met after degraded, because This, exceeded PVA product waste materials need otherwise processed.
Pass through heating so that PVA product waste materials dissolve, the aqueous solution formed after PVA dissolvings, so as to further Carry out Fenton degradation reaction.
Preferably, the temperature of the heating be 100 DEG C~150 DEG C, by the temperature of heating for dissolving be set to 100 DEG C~ 150 DEG C, PVA products waste material caused by nuclear power plant is primarily due to, from different producers and different models, can not be ensured Solution temperature is completely the same, when temperature is more than 100 DEG C, it can be ensured that the PVA of different model different manufacturers can occur completely Dissolving, and if it exceeds 150 DEG C, then it can increase energy consumption.
Water for dissolving PVA is nuclear power plant's demineralized water.
In order to facilitate processing, the usage amount of material transfer workload and equipment in reduction processing, directly in the PVA aqueous solution Middle addition Fenton (Fenton) reagent.
Preferably, Fenton reagent of the present invention is the hydrogen peroxide comprising ferrous ion.Include ferrous ion PVA can be degraded to the weak organic acid solution of small molecular organic acid and intermediate by hydrogen peroxide.
Preferably, the temperature of Fenton's reaction is 90 DEG C~110 DEG C, at such a temperature, not only improves PVA degraded, keeps away again Exempt to cause hydrogen peroxide to seethe with excitement because temperature is too high and volatilize.
Usually, during Fenton's reaction, according to mass ratio, the inventory of hydrogen peroxide is somewhat in excess in PVA, to ensure PVA is degraded completely.
Preferably, according to mass ratio, rate of charge PVA：Hydrogen peroxide=5:6.
The solution for degrading to obtain to Fenton's reaction carries out filtration treatment, filters out the insoluble matter that particle diameter is more than 0.25 μm, and right Insoluble matter is collected, detects radionuclide amount, when radionuclide amount reaches discharging standards, Ke Yipai Put, if unqualified, other processing are carried out after mark.
Heated oxide processing is carried out to the filtrate obtained after filtering, heated oxide processing is mainly by caused by Fenton's reaction Weak organic acid further aoxidizes, and it is converted into carbon dioxide and water and liquid oxygen compound, with reduce the COD in filtrate and BOD values, reach the standard of discharge.
Preferably, the temperature of the heated oxide processing is 600 DEG C~700 DEG C, at such a temperature, can realize weak organic acid Complete oxidation, while energy consumption can be reduced as far as possible.
During heated oxide processing, because temperature is higher, generation carbon monoxide, carbon dioxide and vapor, and an oxygen Change carbon to be directly discharged in air that air pollution can be caused, it is therefore desirable to receive hot gas caused by heated oxide processing Collection, and catalytic oxidation treatment is carried out, carbon monoxide therein is converted into carbon dioxide, then cooling hot gas so that water steams Gas condenses, without being discharged after solidifying gas after testing environmental sound.
Preferably, the catalysis oxidation uses the alloy of noble metal or noble metal as catalyst.
It is further preferred that the catalyst is platinum catalyst or platinum plating metallic catalyst.
Preferably, the temperature of catalysis oxidation is 550 DEG C~650 DEG C.Catalytic activity highest in the temperature range.
Radiological techniques treatment of wastes produced method provided by the invention, realize surface contact agent dose rate<2mSv/h PVA The degraded of product waste material, the accumulation of PVA products waste material in nuclear power plant is avoided, and catabolite is environmentally friendly, radioactivity Activity concentration≤1MBq/m3, COD and BOD values reach country discharge mark；The processing method technique is simple, less energy consumption, is advantageous to save Can emission reduction and environmental protection.
For more effectively explanation technical scheme, illustrate that the embodiment of the present invention is radiated below by multiple embodiments Property technology treatment of wastes produced method.
Embodiment 1
A kind of radiological techniques treatment of wastes produced method, comprises the following steps：
(1) caused PVA protective articles during nuclear power plant's overhaul be collected, transported, sorted and surface exposure dose Rate etc. is detected, and using 2mSv/h surface contact agent dose rate as classification point, is divided into surface contact agent dose rate >=2mSv/h PVA products waste material and surface contact agent dose rate<2mSv/h PVA product waste materials；
(2) by surface contact agent dose rate<2mSv/h PVA products waste material input is held in the device of running water, and to it Heated, heating-up temperature is 100 DEG C, stirring, is dissolved completely in PVA in water；
(3) added into the PVA solution and include the hydrogen peroxide of ferrous ion, wherein PVA and hydrogen peroxide feed intake Mass ratio is 5:6, carry out Fenton's reaction so that PVA is degraded to the weak organic acid solution of small molecular organic acid and intermediate；
(4) solution for treating to obtain in step (3) is cooled to room temperature, carries out multiple times of filtration processing, filters out particle diameter and be more than 0.25 μm of insoluble particles thing, and collect and detect obtained insoluble particles thing；
(5) heated oxide processing is carried out to filtrate, is heated to 600 DEG C, and collect caused gas during heated oxide And vapor, gas and vapor are subjected to catalysis oxidation together, using platinum group metal as catalyst, the temperature of catalysis oxidation For 600 DEG C, after catalysis oxidation, condensation process is carried out to gas and vapor, not solidifying gas, handled simultaneously by high efficiency particulate air filter Detect it is qualified after, discharged into air.Filtered fluid after heated oxide processing, after testing, activity concentration is about 0.8MBq/m3, COD is about 86mg/L, and BOD is about 18mg, meets discharge standard.
Embodiment 2
A kind of radiological techniques treatment of wastes produced method, comprises the following steps：
(1) caused PVA protective articles during nuclear power plant's overhaul be collected, transported, sorted and surface exposure dose Rate etc. is detected, and using 2mSv/h surface contact agent dose rate as classification point, is divided into surface contact agent dose rate >=2mSv/h PVA products waste material and surface contact agent dose rate<2mSv/h PVA product waste materials；
(2) by surface contact agent dose rate<2mSv/h PVA products waste material input is held in the device of running water, and to it Heated, heating-up temperature is 150 DEG C, stirring, is dissolved completely in PVA in water；
(3) added into the PVA solution and include the hydrogen peroxide of ferrous ion, wherein PVA and hydrogen peroxide feed intake Mass ratio is 5:6, carry out Fenton's reaction so that PVA is degraded to the weak organic acid solution of small molecular organic acid and intermediate；
(4) solution for treating to obtain in step (3) is cooled to room temperature, carries out multiple times of filtration processing, filters out particle diameter and be more than 0.25 μm of insoluble particles thing, and collect and detect obtained insoluble particles thing；
(5) heated oxide processing is carried out to filtrate, is heated to 700 DEG C, and collect caused gas during heated oxide And vapor, gas and vapor are subjected to catalysis oxidation together, using platinum group metal as catalyst, the temperature of catalysis oxidation For 600 DEG C, after catalysis oxidation, condensation process is carried out to gas and vapor, not solidifying gas, handled simultaneously by high efficiency particulate air filter Detect it is qualified after, discharged into air.Filtered fluid after heated oxide processing, after testing, activity concentration is about 0.5MBq/m3, COD is about 72mg/L, and BOD is about 25mg, meets discharge standard.
Embodiment 3
A kind of radiological techniques treatment of wastes produced method, comprises the following steps：
(1) caused PVA protective articles during nuclear power plant's overhaul be collected, transported, sorted and surface exposure dose Rate etc. is detected, and using 2mSv/h surface contact agent dose rate as classification point, is divided into surface contact agent dose rate >=2mSv/h PVA products waste material and surface contact agent dose rate<2mSv/h PVA product waste materials；
(2) by surface contact agent dose rate<2mSv/h PVA products waste material input is held in the device of running water, and to it Heated, heating-up temperature is 130 DEG C, stirring, is dissolved completely in PVA in water；
(3) added into the PVA solution and include the hydrogen peroxide of ferrous ion, wherein PVA and hydrogen peroxide feed intake Mass ratio is 5:6, carry out Fenton's reaction so that PVA is degraded to the weak organic acid solution of small molecular organic acid and intermediate；
(4) solution for treating to obtain in step (3) is cooled to room temperature, carries out multiple times of filtration processing, filters out particle diameter and be more than 0.25 μm of insoluble particles thing, and collect and detect obtained insoluble particles thing；
(5) heated oxide processing is carried out to filtrate, is heated to 650 DEG C, and collect caused gas during heated oxide And vapor, gas and vapor are subjected to catalysis oxidation together, using platinum group metal as catalyst, the temperature of catalysis oxidation For 600 DEG C, after catalysis oxidation, condensation process is carried out to gas and vapor, not solidifying gas, handled simultaneously by high efficiency particulate air filter Detect it is qualified after, discharged into air.Filtered fluid after heated oxide processing, after testing, activity concentration is about 0.6MBq/m3, COD is about 83mg/L, and BOD is about 21mg, meets discharge standard.
The foregoing is merely illustrative of the preferred embodiments of the present invention, is not intended to limit the invention, all essences in the present invention All any modification, equivalent and improvement made within refreshing and principle etc., all should be included within protection scope of the present invention.

Claims (8)

  1. A kind of 1. radiological techniques treatment of wastes produced method, it is characterised in that：Including at least following steps：
    By contact agent dose rate in surface caused by nuclear power plant<2mSv/h PVA product waste materials, which are placed in water, to be heated, and is made PVA product waste materials dissolve, and obtain the aqueous solution after PVA dissolvings；
    Fenton reagent is added into the PVA aqueous solution, makes PVA that oxidative degradation occur, obtains degradation solution；
    Filtration treatment is carried out to the degradation solution, filters out the insoluble matter that particle diameter is more than 0.25 μm, and heated oxide is carried out to filtrate Processing, make activity concentration≤1MBq/m of the filtrate3, and COD≤100mg/L, BOD≤30mg；Collect described add The gas of thermal oxidation discharge, catalytic oxidation treatment is carried out to the gas.
  2. 2. radiological techniques treatment of wastes produced method as claimed in claim 1, it is characterised in that：The temperature of the heating For 100 DEG C~150 DEG C.
  3. 3. the radiological techniques treatment of wastes produced method as described in any one of claim 1~2, it is characterised in that：The heating The temperature of oxidation processes is 600 DEG C~700 DEG C.
  4. 4. radiological techniques treatment of wastes produced method as claimed in claim 1, it is characterised in that：The catalysis oxidation is using expensive The alloy of metal or noble metal is as catalyst.
  5. 5. radiological techniques treatment of wastes produced method as claimed in claim 4, it is characterised in that：The catalyst is urged for platinum Agent or platinum plating metallic catalyst.
  6. 6. radiological techniques treatment of wastes produced method as claimed in claim 1, it is characterised in that：Need to carry out the catalysis oxygen The gas for changing processing is carbon monoxide.
  7. 7. radiological techniques treatment of wastes produced method as claimed in claim 1, it is characterised in that：The temperature of the catalysis oxidation For 550 DEG C~650 DEG C.
  8. 8. radiological techniques treatment of wastes produced method as claimed in claim 1, it is characterised in that：The heated oxide processing Afterwards, in addition to vapor caused by heated oxide processing condensation process is carried out.
CN201710762191.9A 2017-08-30 2017-08-30 Radiological techniques treatment of wastes produced method Active CN107658038B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201710762191.9A CN107658038B (en) 2017-08-30 2017-08-30 Radiological techniques treatment of wastes produced method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201710762191.9A CN107658038B (en) 2017-08-30 2017-08-30 Radiological techniques treatment of wastes produced method

Publications (2)

Publication Number Publication Date
CN107658038A true CN107658038A (en) 2018-02-02
CN107658038B CN107658038B (en) 2019-11-01

Family

ID=61128756

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201710762191.9A Active CN107658038B (en) 2017-08-30 2017-08-30 Radiological techniques treatment of wastes produced method

Country Status (1)

Country Link
CN (1) CN107658038B (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112547754A (en) * 2020-11-05 2021-03-26 江苏景泰石油化工装备有限公司 Control method and system of waste treatment system, readable storage medium and programmable controller
CN112820438A (en) * 2020-04-30 2021-05-18 东部技术公司 Chemical oxidation treatment process of PVA waste treatment system
CN112908508A (en) * 2021-01-12 2021-06-04 中国工程物理研究院材料研究所 Method for treating radioactive analysis waste liquid by one-step method
CN113096843A (en) * 2019-12-23 2021-07-09 中广核研究院有限公司 Method for treating radioactive solid waste

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6113195A (en) * 1984-06-28 1986-01-21 住友化学工業株式会社 Method of treating radioactive waste water
US20050061357A1 (en) * 2003-09-23 2005-03-24 Steward John B. Strippable PVA coatings and methods of making and using the same
CN102754167A (en) * 2009-11-17 2012-10-24 汉纳检查及工程有限公司 Disposal and decontamination of radioactive polyvinyl alcohol products
CN106251924A (en) * 2016-01-21 2016-12-21 青岛天和清原科技有限公司 Supercritical water oxidation processes the method for PVA polymeric material
CN106875995A (en) * 2017-01-20 2017-06-20 魏家奎 A kind of method for purifying the degradable PVA products of low-activity in disposal

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6113195A (en) * 1984-06-28 1986-01-21 住友化学工業株式会社 Method of treating radioactive waste water
US20050061357A1 (en) * 2003-09-23 2005-03-24 Steward John B. Strippable PVA coatings and methods of making and using the same
CN102754167A (en) * 2009-11-17 2012-10-24 汉纳检查及工程有限公司 Disposal and decontamination of radioactive polyvinyl alcohol products
CN106251924A (en) * 2016-01-21 2016-12-21 青岛天和清原科技有限公司 Supercritical water oxidation processes the method for PVA polymeric material
CN106875995A (en) * 2017-01-20 2017-06-20 魏家奎 A kind of method for purifying the degradable PVA products of low-activity in disposal

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
俞俊棠 等: "《生物工艺学 下》", 31 May 1992 *
昝云龙: "《大亚湾核电站生产管理从书 维修管理》", 31 May 2003 *

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113096843A (en) * 2019-12-23 2021-07-09 中广核研究院有限公司 Method for treating radioactive solid waste
CN113096843B (en) * 2019-12-23 2024-04-23 中广核研究院有限公司 Method for treating radioactive solid waste
CN112820438A (en) * 2020-04-30 2021-05-18 东部技术公司 Chemical oxidation treatment process of PVA waste treatment system
CN112547754A (en) * 2020-11-05 2021-03-26 江苏景泰石油化工装备有限公司 Control method and system of waste treatment system, readable storage medium and programmable controller
CN112908508A (en) * 2021-01-12 2021-06-04 中国工程物理研究院材料研究所 Method for treating radioactive analysis waste liquid by one-step method
CN112908508B (en) * 2021-01-12 2022-11-04 中国工程物理研究院材料研究所 Method for treating radioactive analysis waste liquid by one-step method

Also Published As

Publication number Publication date
CN107658038B (en) 2019-11-01

Similar Documents

Publication Publication Date Title
CN107658038B (en) Radiological techniques treatment of wastes produced method
Zhang et al. Photocatalysis activation of peroxodisulfate over the supported Fe3O4 catalyst derived from MIL-88A (Fe) for efficient tetracycline hydrochloride degradation
Ganesan et al. Removal of manganese from water by electrocoagulation: adsorption, kinetics and thermodynamic studies
CN105565465B (en) A kind of method of microwave induced carried active carbon catalysis persulfate processing phthalic acid ester waste water
CN204841398U (en) Degradation device who contains low concentration VOCs waste gas
CN105668719B (en) Load the activated carbon catalysis granule electrode and preparation method of cobalt/cobalt oxide
Guo et al. Efficient charge separation in sulfur doped AgFeO2 photocatalyst for enhanced photocatalytic U (VI) reduction: The role of doping and mechanism insights
CN105289521A (en) Preparation method of surface modified pine needle loaded lanthanum hydroxide phosphorus adsorbent
CN113860472B (en) Method for removing pollutants in water by activating peracetic acid with different carbon materials through electron transfer mechanism and application of method
CN106180140B (en) A kind of minimizing technology of Heavy Metal Pollution in Municipal Solid Waste object
CN209548982U (en) A kind of chemical workshop exhaust gas purification and treatment device
Liu et al. Magnetic CuFe2O4 nanoparticles anchored on N-doped carbon for activated peroxymonosulfate removal of oxytetracycline from water: Radical and non-radical pathways
CN107364942A (en) It can be applied to hydro-thermal carbon composite, its preparation method and its application of class Fenton&#39;s reaction
Montazer et al. Synthesis of cuttlebone/carbon quantum dots/nickel oxide nanocomposite for visible light photodegradation of malachite green used for environmental remediation
CN102201272A (en) Method for processing radioactive wastes
CN104258728A (en) Device for flash treatment of volatile organic waste gases
CN110170300A (en) A kind of preparation method of chicken feather modified honeycomb shape active carbon with high specific surface area adsorbent material
CN109847752A (en) Composite catalyzing material photoelectricity, which is aoxidized, by transition bimetallic activates the PEC system that persulfate handles ammonia and produces electricity
CN101585565B (en) Method and apparatus for condensate demineralization
CN109364659A (en) The purification of thallium and recovery method and device in a kind of flue gas during smelting
KR101919200B1 (en) Electrolytic decontamination method capable of regenerative electrolyte
CN109647537B (en) Alpha-ferric oxide polystyrene composite fiber, preparation method and application thereof in photocatalytic degradation of phenol compounds
CN108565037A (en) The catalytic regeneration method of PWR nuclear power plant radioactivity waste oil
CN103521183A (en) Adsorbent for treating acrylonitrile waste water as well as preparation method and application thereof
CN109626514B (en) Carbon ceramic shell-core type three-dimensional particle electrode and preparation method thereof

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant