CN110797132A - Waste resin treatment method for stabilizing radioactive nuclide - Google Patents
Waste resin treatment method for stabilizing radioactive nuclide Download PDFInfo
- Publication number
- CN110797132A CN110797132A CN201911010373.6A CN201911010373A CN110797132A CN 110797132 A CN110797132 A CN 110797132A CN 201911010373 A CN201911010373 A CN 201911010373A CN 110797132 A CN110797132 A CN 110797132A
- Authority
- CN
- China
- Prior art keywords
- waste resin
- stabilizing
- chelating agent
- resin
- polyester
- 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
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
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
-
- 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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/10—Processing by flocculation
-
- 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
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/307—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Inorganic Chemistry (AREA)
- Separation, Recovery Or Treatment Of Waste Materials Containing Plastics (AREA)
- Treatment Of Sludge (AREA)
Abstract
The invention discloses a method for treating waste resin for stabilizing radioactive nuclide, which comprises the steps of primary degradation of waste resin, stabilization of chemical chelating agent and polyester solidification. The initial degradation of the waste resin is to use methylene chloride to pretreat the resin to obtain a loose and porous structure, and then use the microwave assistance of sodium hydroxide (NaOH) to degrade the waste resin; the chemical chelating agent is used for stabilizing radionuclide in the waste resin to form a stable chelate by adding a chelating agent, and the chemical chelating agent is used as a stabilizing agent to fix nuclide; the polyester cure includes Red Mud (RM), micronized clay, and polyester. Compared with the prior art, the invention has the advantages that the treatment mode of stably curing the radionuclide after the waste resin is primarily treated is simple in curing formula, convenient to operate, safe and reliable, strong in practicability of the curing formula, high in compressive strength, very high in impermeability and high-temperature resistance.
Description
Technical Field
The invention relates to the technical field of waste treatment of nuclear power plants, in particular to a method for treating waste resin of stable radionuclide.
Background
Ion exchange resin is used in a primary loop cooling system, a secondary loop condensed water purification system, a spent fuel pool water purification system, a waste water purification system and the like of a reactor, and when the ion exchange resin fails, the reused radioactive nuclide-containing waste resin is called as radioactive waste resin, which is called as waste resin for short. The waste resin is organic waste which generates flammable gases such as H2, CH4, NH3, etc. upon irradiation, pyrolysis, or biodegradation; the waste resin contains polysulfide and nitrogen, and degradation products have stronger corrosivity on equipment and a storage container; the waste resin is a dispersive substance, if the waste resin is not treated, the waste resin is irradiated and decomposed to generate combustible gas in the long-term storage process, and the safety of the waste resin in the long-term storage cannot be ensured, so the waste resin must be subjected to stabilization treatment and packaging to meet the requirements of waste transportation and final disposal. The waste resin is therefore also a radioactive waste that is difficult to handle in nuclear power plants.
The waste resin treatment technology comprises nuclide separation method, solidification, oxidative decomposition, high integrity container, thermal state super compression and the like. The cement curing application is relatively wide, the technology is relatively mature, the process is simple, the cost is low, but the capacity increase ratio of a cured body is large due to the resin package capacity, if the proportion of waste resin is increased, the mechanical strength is possibly reduced, the stability of the cured body is influenced, the long-term safe disposal stability of the waste resin is poor, the leaching rate is high, cracks are easy to generate, and the like, so that the long-term safe disposal is not facilitated. From the viewpoint of achieving waste minimization, the conventional cement setting technology has been challenged by a treatment process having a significant volume reduction effect.
Disclosure of Invention
In order to solve the existing problems, the invention provides a method for treating waste resin of stable radionuclide, which can not only improve the content of waste, but also avoid the leaching of harmful substances, and the solidified material polyester injection has more advantages than the cement and other mixture injection, the solidification speed is fast, the solidified body stability is strong, the solidified body compressive strength is high, the leaching rate is extremely low, and all meet the national standard, therefore, the invention provides a method for treating waste resin of stable radionuclide, which has the following specific steps;
1) primarily degrading waste resin;
the initial degradation of the waste resin comprises the steps of firstly pretreating the resin by dichloromethane DCM to obtain a loose and porous structure, and then degrading the waste resin by the aid of microwaves of sodium hydroxide NaOH;
2) stabilizing a chemical chelating agent;
the chemical chelating agent is used for stabilizing radionuclide in the waste resin to form a stable chelate by adding a chelating agent, and the chemical chelating agent is used as a stabilizing agent to fix nuclide;
3) solidifying the polyester;
the polyester curing comprises red mud RM, micronized clay and polyester.
As a further improvement of the method, the ratio of dichloromethane to the waste resin in the preliminary degradation of the waste resin in the first step is 2: 4-2: 6(w/w), and the pretreatment time of the resin by using dichloromethane for the preliminary degradation is 24-48 h.
As a further improvement of the method, when the waste resin in the first step is primarily degraded, the waste resin is oscillated in a water bath constant temperature oscillator at a certain rotating speed in NaOH solution at normal temperature, the rotating speed in the water bath is 150-200 r/min, the oscillating time in the water bath constant temperature oscillator is 50-60 min, the NaOH concentration of the NaOH in the waste resin primarily degraded by the aid of microwaves of the NaOH is 5-10 mol/L, and the solid-to-liquid ratio of the waste resin to the NaOH in the waste resin primarily degraded is 1: 5.
As a further improvement of the invention, the waste resin is primarily degraded and placed in a microwave oven, heated for a period of time under certain microwave power, heated to 130 ℃, continuously reacted, and cooled to room temperature, wherein the microwave frequency is 200-700W, and the microwave time is 50-60 min.
According to a further improvement of the invention, the chemical chelating agent in the second step is stabilized by adding an organic chelating agent, wherein the organic chelating agent is one or more of dithiocarbamic acid, dithiocarbamic acid dipotassium salt, thiourea or a mixture of citric acid and glycolic acid, the chemical chelating agent stabilizing treatment system is in a weak acid, neutral or weak base condition, and the pH of the mixed solution is 5-8.
As a further improvement of the invention, the chemical chelating agent can be used for stabilizing, in a form of adding a flocculating agent, the flocculating agent can precipitate the chelated radionuclide, not only can accelerate the precipitation of the chelate, but also can flocculate the excessive added chelating agent, the flocculating agent is Polymeric Aluminum Ferric Chloride (PAFC) solution or Polymeric Aluminum Chloride (PAC) solution, and the concentration of the flocculating agent is 10.0mg·mL-1。
As a further improvement of the invention, the red mud RM in the polyester solidification of the third step is waste bauxite with ultra-fine grain diameter, mainly containing alkali metals, iron oxide and hydroxide, aluminum hydroxide, calcium carbonate, titanium and silicon dioxide; the micronized clay MC is soil sediment, and kaolinite and montmorillonite are main clay minerals; the polyester is prepared from polyethylene glycol terephthalate by using cobalt naphthenate as an accelerator and methyl ethyl ketone peroxide as a catalyst, and the ratio of red mud, micronized clay and polyester in polyester curing is 1:1: 2-1: 1: 4.
As a further improvement of the invention, the waste resin is dehydrated radioactive ion exchange resin.
In general, compared with the prior art, the above technical solutions contemplated by the present invention provide a method for treating waste resin to stabilize radionuclides, which includes the steps of preliminary degradation of waste resin, stabilization of chemical chelating agent, and solidification of polyester. The initial degradation of the waste resin is to use methylene chloride to pretreat the resin to obtain a loose and porous structure, and then use the microwave assistance of sodium hydroxide (NaOH) to degrade the waste resin; the chemical chelating agent is used for stabilizing radionuclide in the waste resin to form a stable chelate by adding a chelating agent, and the chemical chelating agent is used as a stabilizing agent to fix nuclide;
the polyester cure includes Red Mud (RM), micronized clay, and polyester. Compared with the prior art, the invention has the advantages that the treatment mode of stably curing the radionuclide after the waste resin is primarily treated is simple in curing formula, convenient to operate, safe and reliable, strong in practicability of the curing formula, high in compressive strength, very high in impermeability and high-temperature resistance.
Detailed Description
The present invention will be described in further detail with reference to specific embodiments below:
the invention provides a method for treating waste resin of stable radionuclide, which can not only improve the content of waste, but also avoid the leaching of harmful substances, and the solidified material polyester injection has more advantages than the injection of cement and other mixtures, and has the advantages of high solidification speed, strong solidified body stability, high solidified body compressive strength and extremely low leaching rate, and all the steps accord with the national standard.
The invention discloses a method for treating waste resin for stabilizing radioactive nuclide, which comprises the steps of primary degradation of waste resin, stabilization of chemical chelating agent and polyester solidification; the process comprises the following steps: removing water from the waste resin, treating with dichloromethane, adding into sodium hydroxide solution, reacting for a while, adjusting pH, adding chelating agent, stabilizing, and curing.
The initial degradation of the waste resin comprises the steps of firstly pretreating the resin by using Dichloromethane (DCM) to obtain a loose and porous structure, and then degrading the waste resin by using the microwave assistance of sodium hydroxide (NaOH); the chemical chelating agent is used for stabilizing radionuclide in the waste resin to form a stable chelate by adding a chelating agent, and the chemical chelating agent is used as a stabilizing agent to fix nuclide; the polyester cure includes Red Mud (RM), micronized clay, and polyester.
Further, the ratio of the dichloromethane to the waste resin in the preliminary degradation of the waste resin is 2: 4-2: 6(w/w), such as 2:4, 2:5 and 2: 6.
And the resin is pretreated by dichloromethane for 24-48 h in the primary degradation.
Further, the concentration of sodium hydroxide (NaOH) in the waste resin preliminary degradation microwave-assisted degradation waste resin is 5-10 mol/L, such as 5mol/L, 6mol/L, 7mol/L, 8mol/L, 9mol/L and 10 mol/L.
The solid-to-liquid ratio of the waste resin to sodium hydroxide (NaOH) in the preliminary degradation of the waste resin is 1: 5;
when the waste resin is primarily degraded, firstly, the waste resin is oscillated in a NaOH solution at normal temperature and a certain rotating speed in a water bath constant temperature oscillator;
preferably, the rotational speed in the water bath is 150 to 200r/min, such as 150r/min, 180r/min and 200 r/min.
Preferably, the oscillation time in a water bath constant temperature oscillator is 50-60 min; for example 50min, 55min and 60 min.
The waste resin is primarily degraded and placed in a microwave oven, heated for a period of time under certain microwave power, heated to 130 ℃, continuously reacted and cooled to room temperature;
preferably, the microwave frequency is 200-700W, such as 200W, 300W, 400W, 500W, 600W, 700W.
Preferably, the microwave time is 50-60 min.
Furthermore, the chemical chelating agent has better stability by adding an organic chelating agent during the stabilization;
wherein the organic chelating agent is one or more of dithiocarbamic acid, dipotassium dithiocarbamic acid, thiourea or a mixture of citric acid and glycolic acid.
Further, the chemical chelating agent stabilizing treatment system is in a weak acid, neutral or weak base condition;
preferably, the pH of the mixture is 5 to 8, for example, pH 5, 6, 7 and 8.
Furthermore, the chemical chelating agent can be added in a form of a flocculating agent during the stabilizing action, and the flocculating agent can precipitate the chelated radionuclide, so that the precipitation of the chelate can be accelerated, and the excessive added chelating agent can be flocculated;
preferably, the flocculant can be a polyaluminum ferric chloride (PAFC) solution or a polyaluminum chloride (PAC) solution, and the concentration is 10.0 mg-mL < -1 >.
Further, said polyester curing medium Red Mud (RM) is ultra-fine particle size waste bauxite containing mainly alkali metals, iron oxides and hydroxides, aluminum hydroxide, calcium carbonate, titanium and silica; the Micronized Clay (MC) is a soil deposit, kaolinite and montmorillonite are the main clay minerals; the polyester is prepared by using polyethylene glycol terephthalate as an accelerating agent in the presence of cobalt naphthenate and using methyl ethyl ketone peroxide as a catalyst;
preferably, the ratio of the red mud, the micronized clay and the polyester in the polyester curing is 1:1:2 to 1:1:4, such as 1:1:2, 1:1:3 and 1:1: 4.
The waste resin is dehydrated radioactive ion exchange resin.
The position of the ultraviolet lamp light source can be arbitrary and is not limited, for example, it can be arranged above the housing 19 of the device.
The above description is only a preferred embodiment of the present invention, and is not intended to limit the present invention in any way, but any modifications or equivalent variations made according to the technical spirit of the present invention are within the scope of the present invention as claimed.
Claims (8)
1. A method for treating waste resin of stable radionuclide comprises the following steps;
1) primarily degrading waste resin;
the initial degradation of the waste resin comprises the steps of firstly pretreating the resin by dichloromethane DCM to obtain a loose and porous structure, and then degrading the waste resin by the aid of microwaves of sodium hydroxide NaOH;
2) stabilizing a chemical chelating agent;
the chemical chelating agent is used for stabilizing radionuclide in the waste resin to form a stable chelate by adding a chelating agent, and the chemical chelating agent is used as a stabilizing agent to fix nuclide;
3) solidifying the polyester;
the polyester curing comprises red mud RM, micronized clay and polyester.
2. The method for treating waste resin for stabilizing radionuclide according to claim 1, characterized in that: the ratio of dichloromethane to waste resin in the preliminary degradation of the waste resin in the first step is 2: 4-2: 6(w/w), and the preliminary degradation is carried out on the resin by using dichloromethane for 24-48 h.
3. The method for treating waste resin for stabilizing radionuclide according to claim 1, characterized in that: when the waste resin in the first step is initially degraded, the waste resin is oscillated in a water bath constant temperature oscillator at a certain rotating speed in a NaOH solution at normal temperature, the rotating speed in the water bath is 150-200 r/min, the oscillating time in the water bath constant temperature oscillator is 50-60 min, the NaOH concentration of the NaOH in the waste resin in the initial degradation of the waste resin is 5-10 mol/L, and the solid-to-liquid ratio of the waste resin to the NaOH in the initial degradation of the waste resin is 1: 5.
4. The method for treating waste resin for stabilizing radionuclide according to claim 3, characterized in that: and (3) primarily degrading the waste resin, placing the waste resin in a microwave oven, heating the waste resin for a period of time under certain microwave power, raising the temperature to 130 ℃, continuing to react, and cooling the waste resin to room temperature, wherein the microwave frequency is 200-700W, and the microwave time is 50-60 min.
5. The method for treating waste resin for stabilizing radionuclide according to claim 1, characterized in that: and stabilizing the chemical chelating agent in the second step by adding an organic chelating agent, wherein the organic chelating agent is one or more of dithiocarbamic acid, dithiocarbamic acid dipotassium salt, thiourea or a mixture of citric acid and glycolic acid, the chemical chelating agent stabilizing treatment system is in a weak acid, neutral or weak base condition, and the pH of the mixed solution is 5-8.
6. The method for treating waste resin for stabilizing radionuclide according to claim 5, characterized in that: the chemical chelating agent can precipitate the chelated radionuclide in a form of adding a flocculating agent during the stabilizing action, not only can accelerate the precipitation of the chelate, but also can flocculate the excessive added chelating agent, and the flocculating agent is polyaluminum ferric chloride (PAFC) solution or Polymeric Aluminum Ferric Chloride (PAFC)Polyaluminum chloride PAC solution with concentration of 10.0 mg/mL-1。
7. The method for treating waste resin for stabilizing radionuclide according to claim 1, characterized in that: the red mud RM in the polyester solidification in the third step is waste bauxite with superfine grain diameter, and mainly contains alkali metal, ferric oxide and hydroxide, aluminum hydroxide, calcium carbonate, titanium and silicon dioxide; the micronized clay MC is soil sediment, and kaolinite and montmorillonite are main clay minerals; the polyester is prepared from polyethylene glycol terephthalate by using cobalt naphthenate as an accelerator and methyl ethyl ketone peroxide as a catalyst, and the ratio of red mud, micronized clay and polyester in polyester curing is 1:1: 2-1: 1: 4.
8. The method for treating a waste resin for stabilizing a radionuclide according to any of claims 1 to 7, characterized in that: the waste resin is dehydrated radioactive ion exchange resin.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201911010373.6A CN110797132B (en) | 2019-10-23 | 2019-10-23 | Waste resin treatment method for stabilizing radioactive nuclide |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201911010373.6A CN110797132B (en) | 2019-10-23 | 2019-10-23 | Waste resin treatment method for stabilizing radioactive nuclide |
Publications (2)
Publication Number | Publication Date |
---|---|
CN110797132A true CN110797132A (en) | 2020-02-14 |
CN110797132B CN110797132B (en) | 2022-03-08 |
Family
ID=69441006
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201911010373.6A Active CN110797132B (en) | 2019-10-23 | 2019-10-23 | Waste resin treatment method for stabilizing radioactive nuclide |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN110797132B (en) |
Citations (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2001208896A (en) * | 2000-01-28 | 2001-08-03 | Inst Nuclear Energy Research Rocaec | Method of cosolidifying low-level radioactive wetting waste generated from boiling water nuclear power plant |
US20100075247A1 (en) * | 2008-09-25 | 2010-03-25 | Xin Jin | Method and preparation of chemically prepared toners |
KR20110068636A (en) * | 2009-12-16 | 2011-06-22 | 삼성정밀화학 주식회사 | Method for preparing toner |
CN103237772A (en) * | 2011-11-25 | 2013-08-07 | 中国广东核电集团有限公司 | Cement curing formulation and method for high-level radioactive boron waste resins from nuclear reactor |
US20140124447A1 (en) * | 2012-11-06 | 2014-05-08 | Thatcher Company | Formulations and methods for removing heavy metals from waste solutions containing chelating agents |
CN104200862A (en) * | 2014-09-03 | 2014-12-10 | 南京大学 | Method for solidifying radioactive spent resin by using fly ash base polymers |
CN107796668A (en) * | 2016-09-07 | 2018-03-13 | 岭澳核电有限公司 | A kind of nuclear power plant's spent resin processing method |
CN109346204A (en) * | 2018-09-29 | 2019-02-15 | 深圳中广核工程设计有限公司 | Radioactive spent resin treatment formulations |
CN110400648A (en) * | 2019-06-20 | 2019-11-01 | 中国辐射防护研究院 | A kind of efficient oxidation processing method of nuclear leve radioactive spent resin |
CN112542259A (en) * | 2020-12-08 | 2021-03-23 | 四川固力铁环保工程有限责任公司 | Microwave catalytic cracking process for waste resin |
-
2019
- 2019-10-23 CN CN201911010373.6A patent/CN110797132B/en active Active
Patent Citations (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2001208896A (en) * | 2000-01-28 | 2001-08-03 | Inst Nuclear Energy Research Rocaec | Method of cosolidifying low-level radioactive wetting waste generated from boiling water nuclear power plant |
US20100075247A1 (en) * | 2008-09-25 | 2010-03-25 | Xin Jin | Method and preparation of chemically prepared toners |
KR20110068636A (en) * | 2009-12-16 | 2011-06-22 | 삼성정밀화학 주식회사 | Method for preparing toner |
CN103237772A (en) * | 2011-11-25 | 2013-08-07 | 中国广东核电集团有限公司 | Cement curing formulation and method for high-level radioactive boron waste resins from nuclear reactor |
US20140124447A1 (en) * | 2012-11-06 | 2014-05-08 | Thatcher Company | Formulations and methods for removing heavy metals from waste solutions containing chelating agents |
CN104200862A (en) * | 2014-09-03 | 2014-12-10 | 南京大学 | Method for solidifying radioactive spent resin by using fly ash base polymers |
CN107796668A (en) * | 2016-09-07 | 2018-03-13 | 岭澳核电有限公司 | A kind of nuclear power plant's spent resin processing method |
CN109346204A (en) * | 2018-09-29 | 2019-02-15 | 深圳中广核工程设计有限公司 | Radioactive spent resin treatment formulations |
CN110400648A (en) * | 2019-06-20 | 2019-11-01 | 中国辐射防护研究院 | A kind of efficient oxidation processing method of nuclear leve radioactive spent resin |
CN112542259A (en) * | 2020-12-08 | 2021-03-23 | 四川固力铁环保工程有限责任公司 | Microwave catalytic cracking process for waste resin |
Also Published As
Publication number | Publication date |
---|---|
CN110797132B (en) | 2022-03-08 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
JPS6046394B2 (en) | Method for solidifying high-level radioactive waste liquid using glass | |
US10930406B2 (en) | Liquid-phase oxidative digestion method for radioactively contaminated carbon-containing material | |
JP2003511710A (en) | Processing method of radioactive graphite | |
CN105741899A (en) | Solidification treatment additive, solidification formula and solidification process for radioactive boron-containing waste liquor | |
CN104766643A (en) | Method for removing thorium ions in rear earth melting wastewater through urea resin | |
CN110797132B (en) | Waste resin treatment method for stabilizing radioactive nuclide | |
JP4414214B2 (en) | Treatment method of waste ion exchange resin | |
CN103949217B (en) | The preparation method of tri-iron tetroxide carbon foam composite and the preparation method of carbon foam | |
JP7095130B2 (en) | Wet decomposition of waste ion exchange resin A method of preparing a curable slurry with waste liquid and using it to solidify / fix other waste, and an improved wet oxidation method of waste ion exchange resin and organic matter. | |
CN110400648A (en) | A kind of efficient oxidation processing method of nuclear leve radioactive spent resin | |
JP2012159419A (en) | Radioactive organic waste solidification processing method | |
Hickel et al. | Reaction of hydroxyl radicals with ammonia in liquid water at elevated temperatures | |
CN103474123B (en) | A kind of nanometer Fe/Mn composite catalyst is used for the method for radioactive spent resin oxygenolysis | |
JP5231975B2 (en) | Solidification method of boric acid waste liquid | |
CN107680704A (en) | A kind of method of microwave cooperating Fenton reagent fast degradation radioactive waste ion exchange resin | |
CN115007190B (en) | Preparation method and application of catalyst for degrading sulfonamides based on singlet oxygen generation | |
CN105679390B (en) | Nuclear power station failure drier mixing volume reduction solidification processing method | |
EP1564188B1 (en) | A method for processing spent ion-exchange resins | |
CN103964659B (en) | A kind of iron containing sludge utilizing Fenton reagent method to produce solidifies the method for leaded mud | |
CN108704239B (en) | Realgar tailing slag stabilization treatment method | |
TWI342789B (en) | ||
US6060635A (en) | Method for treating hazardous waste | |
JPH1090490A (en) | Method for solidification treatment of radioactive liquid waster and device for concentration kneading thereof | |
CN104448178A (en) | Urea-formaldehyde (UF) resin and method for removing boric acid in boron-containing waste liquor by using same | |
TWI839848B (en) | Processing method of radioactive ionic resins |
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 |