CN110364280A - A kind of efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid - Google Patents
A kind of efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid Download PDFInfo
- Publication number
- CN110364280A CN110364280A CN201910536577.7A CN201910536577A CN110364280A CN 110364280 A CN110364280 A CN 110364280A CN 201910536577 A CN201910536577 A CN 201910536577A CN 110364280 A CN110364280 A CN 110364280A
- Authority
- CN
- China
- Prior art keywords
- waste liquid
- molecular sieve
- absorption
- spent resin
- fenton oxidation
- 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.)
- Pending
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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Abstract
The invention belongs to Radwastes treatment technical fields, are related to a kind of efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid.The method includes the following steps: that (1) radioactive spent resin Fenton oxidation waste liquid carries out molecular sieve absorption after filtering removal wherein residue and insoluble matter, (2) waste liquid after molecular sieve absorption carries out the measurement of nucleic activity concentration, if measured value is lower than setting value, to waste liquid direct emission；If measured value is optionally greater than setting value, waste liquid is returned into molecular sieve and is adsorbed.Utilize the efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid of the invention, it can be in the case where not changing former waste liquid characteristic substantially, it realizes and the deep purifying of key characteristic nucleic Co-60, Cs-137, Sr-90 in waste liquid is handled, processed waste liquid can meet direct emission and require (nucleic total activity concentration < 500Bq/L).
Description
Technical field
The invention belongs to Radwastes treatment technical fields, are related to a kind of height of radioactive spent resin Fenton oxidation waste liquid
Imitate adsorption treatment method.
Background technique
The inorganization volume reduction treatment of the radioactive spent resin containing organic matter is the difficult point of Radioactive waste management both at home and abroad at present
One of, the field and range being related to include:
(1) core JG unit keeps in the safe handling of spent resin at present；
(2) nuclear power plant and JG unit have the upgrading of resin cement curing process system；
(3) the following elimination of nuclear facilities will generate the safe handling of spent resin.
The spent resin many places that core military project unit generates at present mostly use tradition in temporary state, the spent resin that nuclear power plant generates
Cement solidification is handled.Cement solidification has the advantages that simple process, technology maturation, processing cost are low, but is used for organic matter
When the processing of graininess spent resin, there are the technical bottlenecks of waste increase-volume and solidified body long-time stability.
Fenton oxidation is a kind of inorganization volume reduction treatment technology of radioactive spent resin, which includes two-stage method technique,
That is: (1) resin oxidative degradation；(2) oxidation generates the processing of waste liquid.Spent resin Fenton oxidation foreign countries have practical application, domestic
The critical oxidation technological parameter of radioactive spent resin is tentatively grasped at present, the oxygenolysis rate of different type Nuclear grade resin can
Up to 99% or more, the COD for aoxidizing waste liquid can be lower than 100mg/L.Therefore, spent resin Fenton oxidation technology engineering at home at present
The key for changing research is to aoxidize the processing of waste liquid.
Spent resin is aoxidized there are two types of the roadmaps of waste liquid, first is that being handled using traditional cement solidification；Second is that adopting
It is handled with advanced deep-purifying method.The former the advantages of is technical maturity, and processing cost is low, and cement solidification carries out at stabilisation
Before reason can directly meet final disposal requirement, but shortcoming is solidification, need using a large amount of chemical reagent to oxidation waste liquid
It is modulated, modulation waste liquid carries out cement solidification after being concentrated by evaporation through low temperature, long period again.Deep purifying is for different useless
Radionuclide is separated with waste liquid, nucleic is adsorbed onto in a small amount of solid dielectric or is reduced to stable state by the characteristic of liquid, should
Method can make up the above-mentioned deficiency of traditional directly cement solidification.
The technology path of radioactive liquid waste deep purifying has two: first is that this method is not using advanced membrane treatment process
Foot place is that the characteristic of the highly selective and waste liquid of film is closely related, needs filtering, ion exchange, micro-filtration even super before film process
The pretreatment such as filter, process procedure is more, and secondary amount of waste is big；Second is that ion exchange and absorption, this method needs to select to inhale using high
The adsorbent of attached property, especially needs selection inorganic ion exchanger, and molecular sieve has preferable physicalchemical structure stability, passes through
Suitable sial ratio molecular sieve adjusted shows efficient ion Selective adsorption to metal ion.Fukushima, Japan accident
Afterwards, it largely uses molecular sieve and adsorbing separation is carried out to Cs-17 in accident radioactive wastewater and Sr-90.
So far, for radioactive spent resin processing, general method is radioactive spent resin oxidation waste liquid in the world
Cement solidification processing is carried out after being concentrated by evaporation.Reported resin Fenton oxidation+waste liquid cement solidification technique waste subtracts
Hold and finally generates 1 barrel or 2 barrels of solidified cement bodies than about 1.5-3, i.e. three barrels of spent resins.
Summary of the invention
The object of the present invention is to provide a kind of efficient absorption processing methods of radioactive spent resin Fenton oxidation waste liquid, with energy
Enough in the case where not changing former waste liquid characteristic substantially, realize to key characteristic nucleic Co-60, Cs-137, Sr-90 in waste liquid
Deep purifying processing.
In order to achieve this, it is useless that the present invention provides a kind of radioactive spent resin Fenton oxidation in the embodiment on basis
The efficient absorption processing method of liquid, the method include the following steps:
(1) radioactive spent resin Fenton oxidation waste liquid (is eliminated or is reduced not after filtering removal wherein residue and insoluble matter
The influence that molten object adsorbs molecular sieve pore passage ion selectivity, the ratio for aoxidizing insoluble matter in waste liquid is about 0.22g/L) divided
Son sieve absorption,
(2) waste liquid after molecular sieve absorption carries out the measurement of nucleic activity concentration, if measured value is lower than setting value, to waste liquid
Direct emission；If measured value is optionally greater than setting value, waste liquid is returned into molecular sieve and is adsorbed.
The characteristic composition of radioactive spent resin Fenton oxidation waste liquid is general as follows:
SO4 2-Concentration is 40-50g/L, Fe2+Concentration is 150-200mg/L, Fe3+Concentration is 1200-1500mg/L, COD value
For 300-30mg/L, pH value 1.0-3.0, conductivity 50-100ms/cm；Aoxidize Co-60, Cs-137, Sr-90 tri- in waste liquid
The radioactive level of kind nucleic is respectively (1.0-9.0) × 106Bq/L、1.0×103-1.0×105Bq/L、1.0×103-1.0
×104Bq/L。
In a preferred embodiment, the present invention provides a kind of efficient suction of radioactive spent resin Fenton oxidation waste liquid
Attached processing method, wherein in step (1), the strainer filtering for being filtered into 10-100 μm of aperture.
In a preferred embodiment, the present invention provides a kind of efficient suction of radioactive spent resin Fenton oxidation waste liquid
Attached processing method, wherein in step (1), the molecular sieve is A type (can keep long-term structural stability in low pH system)
Or H-type molecular sieve, Si/Al ratio are that (when molecular sieve quality and waste liquid volume ratio are 1:20, H-type molecular sieve is to Co-60 and A by 3-5
Type molecular sieve is respectively 99.6%, 99.8% and 97.0%) to the removal rate of Cs-137, Sr-90.
In a preferred embodiment, the present invention provides a kind of efficient suction of radioactive spent resin Fenton oxidation waste liquid
Attached processing method, wherein in step (1), the molecular sieve absorption uses Static Adsorption or Dynamic Adsorption.
In a kind of more preferred embodiment, the present invention provides a kind of height of radioactive spent resin Fenton oxidation waste liquid
Adsorption treatment method is imitated, wherein the Dynamic Adsorption is that stirring/concussion absorption or columns in series adsorb.
The advantages of stirring/concussion absorption is simple process, and molecular sieve effective adsorption capacity is big, and secondary amount of waste is few, cement
It is big to solidify volume inclusion quantity.The advantages of columns in series adsorbs is that the rate of adsorption is fast, but the molding molecular sieve of columns in series adsorption entails, point
It needs to add in son sieve forming process and does not have contributive 20-30% binder to nucleic absorption, molecular sieve is caused effectively to adsorb appearance
Measure small, secondary amount of waste is more, and solidification volume inclusion quantity is smaller.
In a kind of more preferred embodiment, the present invention provides a kind of height of radioactive spent resin Fenton oxidation waste liquid
Adsorption treatment method is imitated, wherein the stirring/concussion absorption liquid-solid ratio is 20-50mL/g, adsorption time 12-24h.
In a kind of more preferred embodiment, the present invention provides a kind of height of radioactive spent resin Fenton oxidation waste liquid
Adsorption treatment method is imitated, wherein the columns in series is adsorbed as H-type molecular sieve column and the columns in series of A type molecular sieve column adsorbs.Point
The ratio of height to diameter of son sieve column can be designed according to the actual treatment amount of waste liquid.
In a preferred embodiment, the present invention provides a kind of efficient suction of radioactive spent resin Fenton oxidation waste liquid
Attached processing method, wherein in step (2), the setting value is 500Bq/L.
In a preferred embodiment, the present invention provides a kind of efficient suction of radioactive spent resin Fenton oxidation waste liquid
Attached processing method, wherein the method further includes following steps:
(3) stabilization processes, place are carried out using cement solidification or fixing means to the molecular sieve for reaching saturated adsorption capacity
Reason product need to meet radioactive-waste disposal and receive requirement.
In a kind of more preferred embodiment, the present invention provides a kind of height of radioactive spent resin Fenton oxidation waste liquid
Imitate adsorption treatment method, wherein in step (3), the matter of cement, molecular sieve, lime, external adding water in cement solidification or fixing means
Amount is than being 1:(0.38-0.42): (0.04-0.06): (0.28-0.32).
The beneficial effects of the present invention are at the efficient absorption using radioactive spent resin Fenton oxidation waste liquid of the invention
Reason method can be realized in the case where not changing former waste liquid characteristic substantially to key characteristic nucleic Co-60, Cs- in waste liquid
137, the deep purifying processing of Sr-90, processed waste liquid can meet direct emission and require (nucleic total activity concentration < 500Bq/
L).The present invention has the advantages that simple process, at low cost, strong applicability, is related to facility and can be processed as waste disposal facilities or small
Type portable processing device is promoted and applied.
Method of the invention, using the high-effect ionic selectivity of inorganic molecule sieve, can be realized to oxygen after simple filtration
Change the deep purifying processing of characteristic nuclide Co-60, Cs-137, Sr-90 in waste liquid.The waste liquid handled through deep purifying can meet directly
It connects emission request (nucleic total activity concentration < 500Bq/L), it is solid that simple cement can be used in the deposed molecular sieve that treatment process generates
Change/fixation carries out terminal processes.This method has the advantages that simple process, at low cost, strong applicability, can be with Fenton oxidation core
Process matching is applied to a large amount of spent resins of nuclear power plant and JG unit or nuclear technology and disperses a small amount of spent resin using unit
Processing can also be applied to the inorganization processing of organic spent resin of general industry generation.
Beneficial effects of the present invention are embodied in:
(1) it is provided by the invention oxidation waste liquid efficient absorption method for resin oxidation waste liquid characteristic (low ph value, it is low to contain
Salt amount), by simple ion exchange adsorption technique, realization radionuclide is efficiently separated with waste liquid system；
(2) oxidation waste liquid efficient absorption method provided by the invention does not need to carry out waste liquid chemistry modulation pretreatment, no
It needs to handle by the evaporation and concentration of long period, nucleic can be adsorbed onto stable solid phase；
(3) oxidation waste liquid efficient absorption method provided by the invention do not influenced by spent resin the types and sources, it can be achieved that
To the deep purifying of tri- kinds of critical nuclides of Co-60, Cs-137, Sr-90 in various types of resins oxidation waste liquid, the removal rate of three kinds of nucleic
It is all larger than 99%, waste liquid can meet direct emission requirement after nucleic removes；
(4) oxidation waste liquid efficient absorption method provided by the invention can flexible choice stirring/concussion absorption or columns in series suction
Attached mode realizes that the adsorbing separation of nucleic, no temperature and pressure requirement, emission-free processing requirement have apparent economical
Property, safety and environment friendly；
(5) the inorganic molecule sieve adsorbant and cement matrix that oxidation waste liquid efficient absorption method provided by the invention uses have
There is good compatibility, the adsorbent for being adsorbed with radionuclide can be used traditional cement solidification or fixing means and carry out terminal
Stabilization processes, meet the final disposal requirement of radioactive waste；
(6) oxidation waste liquid efficient absorption method provided by the invention is making up the same of traditional waste liquid cement solidification technical deficiency
When, adsorbent after cement solidification or fixation, waste volume reduction ratio can realize it is similarly horizontal with conventional cement curing technology, i.e.,
1.5-3 again.
Detailed description of the invention
Fig. 1 is the process of the efficient absorption processing method of illustrative radioactive spent resin Fenton oxidation waste liquid of the invention
Figure.
Fig. 2 connects in the efficient absorption processing method for illustrative radioactive spent resin Fenton oxidation waste liquid of the invention
Column adsorption process figure.
Specific embodiment
A specific embodiment of the invention is further illustrated with reference to embodiments.
Embodiment 1: the efficient absorption of radioactive spent resin Fenton oxidation waste liquid handles (one)
The characteristic composition of radioactive spent resin Fenton oxidation waste liquid is as follows:
SO4 2-Concentration is 47g/L, Fe2+Concentration is 175mg/L, Fe3+Concentration is 1300mg/L, COD value 200mg/L, pH
Value is 2.5, conductivity 80ms/cm；Aoxidize the radioactive level difference of tri- kinds of nucleic of Co-60, Cs-137, Sr-90 in waste liquid
For (1.5-9.0) × 106Bq/L、1.0×104-2.0×105Bq/L、1.0×103-1.0×104Bq/L。
The efficient absorption process method step of the radioactive spent resin Fenton oxidation waste liquid is as follows:
(1) radioactive spent resin Fenton oxidation waste liquid is after filtering removes wherein residue and insoluble matter (for aperture 10-100 μ
The strainer filtering of m, the ratio for aoxidizing insoluble matter in waste liquid is about 0.22g/L) carry out molecular sieve absorption.Molecular sieve absorption uses 4A
Type molecular sieve is stirred at room temperature/shakes absorption, and absorption liquid-solid ratio is 20-50mL/g, adsorption time 12-24h.
(2) waste liquid after molecular sieve absorption carries out the measurement of nucleic activity concentration, if measured value is lower than setting value, (setting value is
500Bq/L), then to waste liquid direct emission；If measured value is optionally greater than setting value, waste liquid is returned into molecular sieve and is inhaled
It is attached.
(3) stabilization processes, place are carried out using cement solidification or fixing means to the molecular sieve for reaching saturated adsorption capacity
Reason product need to meet radioactive-waste disposal and receive requirement.Cement in processing, molecular sieve, lime, external adding water mass ratio be 1:
0.38:0.04:0.28。
Embodiment 2: the efficient absorption of radioactive spent resin Fenton oxidation waste liquid handles (two)
The characteristic composition of radioactive spent resin Fenton oxidation waste liquid is as follows:
SO4 2-Concentration is 47g/L, Fe2+Concentration is 175mg/L, Fe3+Concentration is 1300mg/L, COD value 200mg/L, pH
Value is 2.5, conductivity 80ms/cm；Aoxidize the radioactive level difference of tri- kinds of nucleic of Co-60, Cs-137, Sr-90 in waste liquid
For (1.5-9.0) × 106Bq/L、1.0×104-2.0×105Bq/L、1.0×103-1.0×104Bq/L。
The efficient absorption process method step of the radioactive spent resin Fenton oxidation waste liquid is as follows:
(1) radioactive spent resin Fenton oxidation waste liquid is after filtering removes wherein residue and insoluble matter (for aperture 10-100 μ
The strainer filtering of m, the ratio for aoxidizing insoluble matter in waste liquid is about 0.22g/L) carry out molecular sieve absorption.Molecular sieve absorption uses H5
The columns in series of type molecular sieve column and 4A type molecular sieve column adsorbs (as shown in Figure 2).
(2) waste liquid after molecular sieve absorption carries out the measurement of nucleic activity concentration, if measured value is lower than setting value, (setting value is
500Bq/L), then to waste liquid direct emission；If measured value is optionally greater than setting value, waste liquid is returned into molecular sieve and is inhaled
It is attached.
(3) stabilization processes, place are carried out using cement solidification or fixing means to the molecular sieve for reaching saturated adsorption capacity
Reason product need to meet radioactive-waste disposal and receive requirement.Cement in processing, molecular sieve, lime, external adding water mass ratio be 1:
0.42:0.06:0.32。
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
Mind and range.If in this way, belonging to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention
Within enclosing, then the present invention is also intended to include these modifications and variations.Above-described embodiment or embodiment are only to the present invention
For example, the present invention can also be implemented with other ad hoc fashions or other particular form, without departing from of the invention
Main idea or substantive characteristics.Therefore, the embodiment of description is regarded as illustrative and non-limiting in any way.This
The range of invention should be illustrated that any variation equivalent with the intention and range of claim also should include by appended claims
Within the scope of the invention.
Claims (10)
1. a kind of efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid, which is characterized in that the method packet
Include following steps:
(1) radioactive spent resin Fenton oxidation waste liquid carries out molecular sieve absorption after filtering removal wherein residue and insoluble matter,
(2) waste liquid after molecular sieve absorption carries out the measurement of nucleic activity concentration, direct to waste liquid if measured value is lower than setting value
Discharge；If measured value is optionally greater than setting value, waste liquid is returned into molecular sieve and is adsorbed.
2. according to the method described in claim 1, it is characterized by: in step (1), described 10-100 μm of the aperture that is filtered into
Strainer filtering.
3. according to the method described in claim 1, it is characterized by: the molecular sieve is A type or H-type molecule in step (1)
Sieve, Si/Al ratio 3-5.
4. according to the method described in claim 1, it is characterized by: the molecular sieve absorption is inhaled using static in step (1)
Attached or Dynamic Adsorption.
5. according to the method described in claim 4, it is characterized by: the Dynamic Adsorption is stirring/concussion absorption or series connection
Column absorption.
6. according to the method described in claim 5, it is characterized by: the stirring/concussion absorption liquid-solid ratio is 20-
50mL/g, adsorption time 12-24h.
7. according to the method described in claim 5, it is characterized by: the columns in series is adsorbed as H-type molecular sieve column and A type point
The columns in series absorption of son sieve column.
8. according to the method described in claim 1, it is characterized by: the setting value is 500Bq/L in step (2).
9. the method according to claim 1, wherein the method further includes following steps:
(3) stabilization processes are carried out using cement solidification or fixing means to the molecular sieve for reaching saturated adsorption capacity.
10. according to the method described in claim 9, it is characterized by: in step (3), cement in cement solidification or fixing means,
Molecular sieve, lime, external adding water mass ratio be 1:(0.38-0.42): (0.04-0.06): (0.28-0.32).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910536577.7A CN110364280A (en) | 2019-06-20 | 2019-06-20 | A kind of efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910536577.7A CN110364280A (en) | 2019-06-20 | 2019-06-20 | A kind of efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN110364280A true CN110364280A (en) | 2019-10-22 |
Family
ID=68216461
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910536577.7A Pending CN110364280A (en) | 2019-06-20 | 2019-06-20 | A kind of efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110364280A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112777767A (en) * | 2020-12-25 | 2021-05-11 | 济南大学 | Radioactive iodine nuclide adsorption treatment method |
| 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 |
Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013072871A (en) * | 2011-09-27 | 2013-04-22 | Shinji Masuyama | Emergency improvement treatment method for radioactive waste liquid in big accident and contamination sample in peripheral environment |
| US20140378734A1 (en) * | 2013-06-21 | 2014-12-25 | Hitachi-Ge Nuclear Energy, Ltd. | Radioactive Organic Waste Treatment Method and System |
| JP2015021856A (en) * | 2013-07-19 | 2015-02-02 | 株式会社タクマ | System and method for removing cesium contained in waste |
| CN104835545A (en) * | 2015-03-19 | 2015-08-12 | 西南科技大学 | Method for deeply purifying and recovering hyperhaline fluoric-u radioactive waste solution |
| US20150238932A1 (en) * | 2014-02-25 | 2015-08-27 | Institute Of Nuclear Energy Research Atomic Energy Council, Executive Yuan | Method for granulation of absorbent and adsorbent granules prepared by the same |
| CN105617982A (en) * | 2016-02-24 | 2016-06-01 | 清华大学 | Inorganic adsorbent for removing 110mAg in radioactive water and preparing method thereof |
| US20160211040A1 (en) * | 2013-08-23 | 2016-07-21 | Hitachi-Ge Nuclear Energy, Ltd. | Method of Treating Radioactive Liquid Waste and Radioactive Liquid Waste Treatment Apparatus |
| CN107195352A (en) * | 2017-05-24 | 2017-09-22 | 中国核电工程有限公司 | A kind of nuclear power plant's radioactive liquid waste and its secondary waste treatment system |
| JP2018119794A (en) * | 2017-01-23 | 2018-08-02 | 三菱重工業株式会社 | Waste resin processing method and waste resin processing system |
| CN108735324A (en) * | 2017-11-23 | 2018-11-02 | 江苏核电有限公司 | A kind of off-line equipment for the cooling of spent fuel transport container helium purification |
| TWI643208B (en) * | 2017-07-27 | 2018-12-01 | 行政院原子能委員會核能研究所 | Apparatus of treating radioactive waste of molybdenum-99 |
| CN109859875A (en) * | 2019-01-16 | 2019-06-07 | 中国辐射防护研究院 | A kind of decontamination solution prosecutor method of Spent Radioactive lubricating oil |
-
2019
- 2019-06-20 CN CN201910536577.7A patent/CN110364280A/en active Pending
Patent Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013072871A (en) * | 2011-09-27 | 2013-04-22 | Shinji Masuyama | Emergency improvement treatment method for radioactive waste liquid in big accident and contamination sample in peripheral environment |
| US20140378734A1 (en) * | 2013-06-21 | 2014-12-25 | Hitachi-Ge Nuclear Energy, Ltd. | Radioactive Organic Waste Treatment Method and System |
| JP2015021856A (en) * | 2013-07-19 | 2015-02-02 | 株式会社タクマ | System and method for removing cesium contained in waste |
| US20160211040A1 (en) * | 2013-08-23 | 2016-07-21 | Hitachi-Ge Nuclear Energy, Ltd. | Method of Treating Radioactive Liquid Waste and Radioactive Liquid Waste Treatment Apparatus |
| US20150238932A1 (en) * | 2014-02-25 | 2015-08-27 | Institute Of Nuclear Energy Research Atomic Energy Council, Executive Yuan | Method for granulation of absorbent and adsorbent granules prepared by the same |
| CN104835545A (en) * | 2015-03-19 | 2015-08-12 | 西南科技大学 | Method for deeply purifying and recovering hyperhaline fluoric-u radioactive waste solution |
| CN105617982A (en) * | 2016-02-24 | 2016-06-01 | 清华大学 | Inorganic adsorbent for removing 110mAg in radioactive water and preparing method thereof |
| JP2018119794A (en) * | 2017-01-23 | 2018-08-02 | 三菱重工業株式会社 | Waste resin processing method and waste resin processing system |
| CN107195352A (en) * | 2017-05-24 | 2017-09-22 | 中国核电工程有限公司 | A kind of nuclear power plant's radioactive liquid waste and its secondary waste treatment system |
| TWI643208B (en) * | 2017-07-27 | 2018-12-01 | 行政院原子能委員會核能研究所 | Apparatus of treating radioactive waste of molybdenum-99 |
| CN108735324A (en) * | 2017-11-23 | 2018-11-02 | 江苏核电有限公司 | A kind of off-line equipment for the cooling of spent fuel transport container helium purification |
| CN109859875A (en) * | 2019-01-16 | 2019-06-07 | 中国辐射防护研究院 | A kind of decontamination solution prosecutor method of Spent Radioactive lubricating oil |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112777767A (en) * | 2020-12-25 | 2021-05-11 | 济南大学 | Radioactive iodine nuclide adsorption treatment method |
| CN112777767B (en) * | 2020-12-25 | 2022-07-22 | 济南大学 | Radioactive iodine nuclide adsorption treatment method |
| 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 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Liu et al. | Adsorption removal of cesium from drinking waters: A mini review on use of biosorbents and other adsorbents | |
| CN108160048B (en) | Large-scale preparation method of high-stability cesium removal adsorbent, and product and application thereof | |
| CN104900286B (en) | By Spent Radioactive water process to the horizontal system of natural background radioactivity and application | |
| Weerasekara et al. | Metal oxide enhanced microfiltration for the selective removal of Co and Sr ions from nuclear laundry wastewater | |
| Han et al. | Removal of cesium from simulated liquid waste with countercurrent two-stage adsorption followed by microfiltration | |
| KR101978499B1 (en) | A adsorbent based on hollow prussian blue magnetic nanoparticles for radioactive cesium, and method of manufacturing the same | |
| CN103274757B (en) | Function ceramic material for efficiently filtering radioactive iodine and cesium, and preparation method thereof | |
| Zhang et al. | Enhanced removal of iodide ions by nano Cu2O/Cu modified activated carbon from simulated wastewater with improved countercurrent two-stage adsorption | |
| CN110364280A (en) | A kind of efficient absorption processing method of radioactive spent resin Fenton oxidation waste liquid | |
| CN105692758A (en) | Poly-tannic acid coated Fe3O4 magnetic adsorbent for removing Hg2+ and Pb2+ | |
| CN104291489A (en) | Treatment method for process wastewater in preparation of high-temperature gas-cooled reactor element core | |
| Ye et al. | Preparation of a GO/PB-modified nanofiltration membrane for removal of radioactive cesium and strontium from water | |
| Vanderheyden et al. | Adsorption of cesium on different types of activated carbon | |
| CN113877517A (en) | Bismuth sulfide aerogel adsorbent for removing radioactive iodine and preparation method and application thereof | |
| CN105944658B (en) | Preparation method of granular cesium removal inorganic ion adsorbent, product and application | |
| CN101894597B (en) | Pretreatment method for radioactive wastewater | |
| US4720422A (en) | Material for collecting radionuclides and heavy metals | |
| CN105107478A (en) | Zirconium-loaded organic hybridizing adsorbent capable of removing radioactive caesium in water as well as preparation and use method of zirconium-loaded organic hybridizing adsorbent | |
| Sun et al. | Efficient Co‐Adsorption and Highly Selective Separation of Cs+ and Sr2+ with a K+‐Activated Niobium Germanate by the pH Control | |
| JP6074242B2 (en) | Radiocesium decontamination method and apparatus | |
| CN103500594B (en) | Low radioactive waste liquid " absorption-solidification " integrated processing system and technique | |
| JP2013024812A (en) | Processing method of radioactive cesium polluted solid | |
| Toropov et al. | The use of composite ferrocyanide materials for treatment of high salinity liquid radioactive wastes rich in cesium isotopes | |
| KR102637534B1 (en) | A manufacturing method of 2D-type iodine adsorption filter | |
| KR101618346B1 (en) | Manufacturing method of soil fixation agents with adhesion of radionuclide |
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 |