CN105976886A - Radioactive waste curing method - Google Patents
Radioactive waste curing method Download PDFInfo
- Publication number
- CN105976886A CN105976886A CN201610304836.XA CN201610304836A CN105976886A CN 105976886 A CN105976886 A CN 105976886A CN 201610304836 A CN201610304836 A CN 201610304836A CN 105976886 A CN105976886 A CN 105976886A
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- China
- Prior art keywords
- radwaste
- colophonium
- curing
- asphalt
- dried
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Classifications
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- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
The invention relates to a radioactive waste curing method carried out in a ventilating condition; the method comprises the following steps: waste drying, i.e., drying to-be-processed radioactive waste; asphalt fusing, i.e., heating to fuse the selected asphalt; mixing, i.e., evenly mixing dried radioactive waste with fused asphalt; cooling solidification, i.e., cooling the mixture of dried radioactive waste and fused asphalt for solidification, thus forming an asphalt firming body waste bag. The curing method is simple and easy, high in volume reduction ratio, and the formed asphalt firming body is good in stability, thus satisfying GB 14569.3 <low and medium level radioactivity firming body performance requirement-asphalt firming body> requirements, and the asphalt firming body waste bag can satisfy our country radioactive waste near-surface disposal standard requirements.
Description
Technical field
The invention belongs to Radwastes treatment technical field, be specifically related to consolidating of a kind of radwaste
Change method.
Background technology
Radioactive spent resin is one of major radiation refuse of nuclear power plant's operation generation, current China core
The radioactive spent resin that power plant produces uses at conventional cement cured and hot debulking methods mostly
Reason.
Use cement solidification PROCESS FOR TREATMENT radioactive spent resin, although the firming body produced disclosure satisfy that
The requirement of GB 14569.1 " Intermediate Level Radioactive firming body performance requirement solidified cement body low, middle ",
But cement solidification processes and there is problems in that
A. due to cement solidification, the containing amount of radioactive spent resin is restricted, giving up after therefore processing
Object increase-volume is relatively big, usually 3 times or more of spent resin volume；
B. the nucleic leaching rate of cement-solidified waste body is higher；
C. owing to the differences such as radwaste composition, Wuli-Shili-Renli system approach and composition are (such as yin, yang tree
The ratio of fat, concentrated solution salinity difference etc.) cause cement formula be difficult in adapt to different waste type and
The refuse of composition processes；
D. having the characteristic of dehydration shrinkage, imbibition due to resin, therefore spent resin cement solidification body is long
The phase stability of storage there is also problem.
Use hot debulking methods to process, be first radioactive spent resin to be dried and be compacted, then
Fix compacting cake loading pail for used dressings carries out cement.Although this processing method self has bigger refuse
Volume reduction rate, but China can not be met owing to adopting the cement immobilized waste bag processing generation in this way
The requirement of radwaste near surface disposal, in addition it is also necessary to load high integrality container and carry out secondary package,
Hence in so that the volume of final refuse body and cost of disposal increase considerably.
The problems referred to above, more preferable radwaste can be overcome therefore, it is necessary to research and develop out
Processing method.
Summary of the invention
For defect present in prior art, it is an object of the invention to provide a kind of radwaste
Curing, this curing is simple and easy to do, volume reduction ratio is high, and the bitumen solidification body formed is stable
Property is good, meets GB 14569.3 " Intermediate Level Radioactive firming body performance requirement bitumen solidification body low, middle "
Requirement, bitumen solidification body refuse bag can meet the near surface disposal standard of China's radwaste want
Ask.
For reaching object above, the technical solution used in the present invention is: the solidification of a kind of radwaste
Method, described curing comprises the following steps:
Refuse is dried: be dried by pending radwaste；
Asphalt melting: selected Colophonium, and by selected Colophonium heating, make fusing；
Mixing: the Colophonium of dry radwaste and fusing is mixed；
Cooled and solidified: the mixture of dry radwaste and the Colophonium of fusing is cooled down, makes solidification,
Form bitumen solidification body refuse bag.
Further, before refuse is dried, if pending radwaste contain more free water (as
The conveying water of spent resin), then should carry out being dehydrated water content in advance and be less than predetermined value, then be dried.
Further, in refuse drying steps, by control baking temperature make radwaste volume reduction and
Loss of weight.
Further, in asphalt melting step, it is appropriate to Colophonium admittedly according to softening point and needle penetration are selected
The asphalt variety changed.
Further, in asphalt melting step, fusion temperature is 100-130 DEG C.
Further, in blend step, the radwaste being dried and the Colophonium of fusing are at 100-130 DEG C
Under mix, be dried radwaste and fusing Colophonium Mixing ratio by weight be about
2/3-1/1.In order to meet GB 14569.3, " Intermediate Level Radioactive firming body performance requirement low, middle drips
Blue or green firming body " softening point requirement, suitable additive can be added in mixed process.
Further, blend step is carried out at blender, and cooled and solidified step is carried out in waste canister,
Or, blend step and cooled and solidified step are all carried out in waste canister.
Further, described radwaste is radioactive spent resin, Spent Radioactive filter medium, radiation
Property mud, radioactive incineration ash or radioactivity salinity.
Before using the inventive method to process refuse, should confirm that processed refuse mixes with the heated bitumen of fusing
The adaptability closed.Should avoid use bitumen solidification process refuse contain a large amount of oxidant (as ammonium nitrate,
Sodium nitrate etc.), unless confirmed that processing procedure and refuse body are safe.Oxygen in suggestion radwaste
Agent content is less than 10wt%.
The curing of a kind of radwaste that the present invention provides has the advantage that
The first, refuse volume reduction effect is notable.
In bitumen solidification body, the containing rate of dried refuse is big, compared with former Waste volume, and total volume reduction ratio
Up to 1.3 or higher.
The second, economic benefit is obvious.
The cost of Radioactive waste management mainly includes that refuse processes (taking containing container), stores, transports
And disposal costs, due to the fact that last Waste volume significantly reduces, therefore, the container of refuse takes,
Storage, transport and disposal costs substantially reduce, and compared with conventional cement solidification, are about reduced to 1/5
Below.
3rd, operability is good.
Between Colophonium and most refuse, chemical reaction will not occur, use Colophonium as dry refuse
Containing medium, only by controlling temperature and being simply mixed and just can realize curing operation.
4th, firming body good stability.
Owing to Colophonium has good physics, chemical stability, and there is good hydrophobic properties,
Radwaste can be isolated from the outside, it is to avoid what solidified cement body refuse body stability reduced lacks
Point.
5th, wide adaptability.The method of the present invention may be used for processing the Spent Radioactive that nuclear power plant produces
Resin, useless filter medium (waste active carbon and zeolite etc.), mud, burning ash and salt grade.
Accompanying drawing explanation
Fig. 1 is the stream of a kind of embodiment of the curing of a kind of radwaste that the present invention provides
Journey schematic diagram；
Fig. 2 is the another embodiment of the curing of a kind of radwaste that the present invention provides
Schematic flow sheet.
Detailed description of the invention
The invention will be further described with detailed description of the invention below in conjunction with the accompanying drawings.
The invention provides the curing of a kind of radwaste, described curing is at ventilated environment
In carry out, comprise the following steps:
Refuse is dried: be dried by pending radwaste, collects expellant gas；
Asphalt melting: by selected Colophonium heating, make fusing；
Mixing: make the Colophonium mix homogeneously of radwaste and the fusing being dried；
Cooled and solidified: the mixture of dry radwaste and the Colophonium of fusing is cooled down, makes solidification,
Form bitumen solidification body refuse bag.
Before the refuse drying steps of the present invention, if pending radwaste contains more free water,
Then should carry out in advance being dehydrated to water content less than predetermined value, then be dried, then be dried.
Additionally, in refuse drying steps, the height of baking temperature can be controlled according to actual needs.Should pass through
Control baking temperature makes radwaste volume reduction and loss of weight, and (volume reduction amount and the loss of weight amount of dissimilar refuse have
Institute is different).Refuse dry run produce steam and other gases be collected, purify, detect and
Discharge.
It is proposed that select suitable asphalt variety according to softening point and needle penetration.
The fusion temperature of Colophonium can be controlled in 100-130 DEG C.
In the blend step of the present invention, the radwaste being dried and the Colophonium of fusing are at 100-130 DEG C
Under mix, be dried radwaste and fusing Colophonium Mixing ratio by weight be about
2/3-1/1.In order to meet GB 14569.3, " Intermediate Level Radioactive firming body performance requirement low, middle drips
Blue or green firming body " softening point requirement, suitable additive can be added in mixed process.
In one embodiment of the invention, blend step can be carried out at blender, cooled and solidified
Step can be carried out in waste canister.
In another embodiment of the invention, blend step and cooled and solidified step all can be useless
Container is carried out.
Should keep good logical at asphalt melting and dry radwaste in molten asphalt mixed process
Wind, to avoid increasing fire risk because of the gathering of pitch volatiles.
The method of the present invention is applicable to process radioactive spent resin, Spent Radioactive filter medium, radioactivity
Mud, radioactive incineration ash or radioactivity salinity.If containing ammonium nitrate or nitre in described radwaste
Acid sodium class oxidant, then oxygenate content should be less than 10wt%, to ensure bitumen solidification process and Colophonium
The safety of firming body.
It addition, radioactive concentration ＜ 3.7 × 10 in radwaste must be ensured10Bq/kg.Correlational study is demonstrate,proved
Bright, when radiation dose is less than 107Gy(109Rad) time, during Colophonium can be successfully used to contain,
Low-level radioactive waste.It should be noted that according to GB 14569.3 " Intermediate Level Radioactive low, middle
Solidification of waste body performance requirement bitumen solidification body " relevant regulations, when bitumen solidification body is in 300a
Cumulative absorbed dose is more than 1 × 104During Gy, the resistance to radiation test of firming body should be simulated.
The method that the radioactivity resin produced with nuclear power plant below illustrates the present invention.
Embodiment 1
Fig. 1 shows that the set of device realizing the inventive method, described device include exsiccator, blender
And waste canister.Concrete curing comprises the following steps:
1) radioactive spent resin is first sent to exsiccator, and the filter arranged by exsiccator bottom is entered
Row dehydration is less than predetermined value to water content.
2), after dehydration, radioactive spent resin is dried at a temperature of 100-250 DEG C.
Generally baking temperature is the highest, and drying time is the longest, the minimizing of the volume and weight of radioactive spent resin
Measure the biggest.Radioactive spent resin volume and weight after drying generally can be reduced to less than 1/2nd.
The dry height that can control baking temperature according to actual needs of other radwastes.
Radioactive spent resin is dried the gas of generation and is mainly water vapour and a part of spent resin active component
(such as trimethylamine etc.), therefore uses the method for condensation and spray washing be collected and process, prevents it
It is directly discharged in environment pollute.
3) suitable asphalt variety is selected, then molten asphalt at 100-130 DEG C.
4) Colophonium of fusing is joined in blender, then be also added to mix by dry radioactive spent resin
In clutch, at 100-130 DEG C of mix homogeneously.The radioactive spent resin being dried and the mixing ratio of the Colophonium of fusing
Example is about 2/3 (weight ratio).
5) mixture of mixed uniformly dry refuse Yu the Colophonium of fusing is filled in waste canister,
Bitumen solidification body refuse bag is formed after natural cooling solidification.
Embodiment 2
Fig. 2 shows that the set of device realizing the inventive method, described device include exsiccator and refuse
Container.
Concrete curing refers to embodiment 1, except for the difference that, blend step and cooled and solidified step
Suddenly all carry out in waste canister.
The present invention uses bitumen solidification to process radioactive spent resin or other refuses, melts owing to controlling Colophonium
Change and the operation temperature relatively low (100-130 DEG C) of mixing, in the mixture without or with little nitre
The strong oxidizers such as acid sodium, and using the ventilation being dried and keeping in bitumen solidification processing procedure good,
The most unlikely breaking out of fire accident.Even so, if desired, also should arrange to put out a fire accordingly and be
System, in case the generation of fire incident.
Above-described embodiment is the illustration to the present invention, and the present invention can also be with other certain party
Formula or other particular form are implemented, without departing from idea of the invention or substitutive characteristics.Therefore, retouch
The embodiment stated in terms of any from the point of view of be regarded as illustrative rather than determinate.The model of the present invention
Enclosing and should be illustrated by appended claims, the change of any and intention of claim and scope equivalence is also
Should be within the scope of the present invention.
Claims (8)
1. the curing of a radwaste (is retouched below as a example by processing radioactive spent resin
State), it is characterised in that comprise the following steps:
Refuse is dried: be dried by pending radwaste；
Asphalt melting: selected Colophonium, and by selected Colophonium heating, make fusing；
Mixing: make the Colophonium mix homogeneously of radwaste and the fusing being dried；
Cooled and solidified: the mixture of dry radwaste and the Colophonium of fusing is cooled down, makes solidification,
Form bitumen solidification body refuse bag.
Curing the most according to claim 1, it is characterised in that in refuse drying steps, if
When the content of the free water of pending radwaste exceedes predetermined value, the most in advance radwaste is entered
Row dehydration is less than predetermined value to water content, then is dried.
Curing the most according to claim 1, it is characterised in that in refuse drying steps is logical
Crossing control baking temperature makes the moisture contained by refuse evaporate, it is achieved radwaste volume reduction and loss of weight, for
The moisture that refuse dry run produces is collected, purifies, detects and discharges.
Curing the most according to claim 1, it is characterised in that according to the softening point of Colophonium and
Needle penetration selectes asphalt variety.
Curing the most according to claim 1, it is characterised in that in asphalt melting step, molten
The temperature changed is 100-130 DEG C.
Curing the most according to claim 1, it is characterised in that in blend step, is dried
The Colophonium of radwaste and fusing mixes at 100-130 DEG C, and the radwaste being dried is with molten
The Mixing ratio by weight of the Colophonium changed is 2/3-1/1.
7. according to the arbitrary described curing of claim 1-6, it is characterised in that blend step is mixed
Clutch is carried out, and cooled and solidified step is carried out in waste canister or blend step and cooled and solidified step all exist
Waste canister is carried out.
Curing the most according to claim 1, it is characterised in that described radwaste is for putting
Penetrating property spent resin, Spent Radioactive filter medium, radioactivity mud, radioactive incineration ash or radioactivity salinity,
In described radwaste, oxygenate content is less than 10wt%, and described oxidant is ammonium nitrate or sodium nitrate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610304836.XA CN105976886A (en) | 2016-05-10 | 2016-05-10 | Radioactive waste curing method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610304836.XA CN105976886A (en) | 2016-05-10 | 2016-05-10 | Radioactive waste curing method |
Publications (1)
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|---|---|
| CN105976886A true CN105976886A (en) | 2016-09-28 |
Family
ID=56991551
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| CN201610304836.XA Pending CN105976886A (en) | 2016-05-10 | 2016-05-10 | Radioactive waste curing method |
Country Status (1)
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106384614A (en) * | 2016-10-17 | 2017-02-08 | 上海核工程研究设计院 | Vacuum drying method for radioactive waste resin |
| CN107626717A (en) * | 2017-09-28 | 2018-01-26 | 重庆天志环保有限公司 | A kind of bitumen solidification technique of hazardous waste |
| CN108490905A (en) * | 2018-05-14 | 2018-09-04 | 镇江新区固废处置股份有限公司 | A kind of solidification of waste DCS control methods |
| CN109903876A (en) * | 2017-03-10 | 2019-06-18 | 清华大学 | Radioactive spent resin cement solidification slurry and preparation method thereof |
| CN110085342A (en) * | 2019-04-23 | 2019-08-02 | 中国核电工程有限公司 | The retired method of Spent Radioactive liquid storage tank |
| CN110211721A (en) * | 2019-07-11 | 2019-09-06 | 中国工程物理研究院应用电子学研究所 | A kind of drying device and drying means for reactor core wastewater treatment based on microwave |
| CN110648776A (en) * | 2019-06-12 | 2020-01-03 | 中国核电工程有限公司 | Method for solidifying radioactive waste and application thereof |
| CN110890165A (en) * | 2019-10-23 | 2020-03-17 | 江苏中海华核环保有限公司 | Combined treatment device and treatment method for radioactive waste resin |
| CN111066094A (en) * | 2018-07-12 | 2020-04-24 | 原子能股份公司 | Waste ion exchange resin treatment method and device |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106384614A (en) * | 2016-10-17 | 2017-02-08 | 上海核工程研究设计院 | Vacuum drying method for radioactive waste resin |
| CN109903876A (en) * | 2017-03-10 | 2019-06-18 | 清华大学 | Radioactive spent resin cement solidification slurry and preparation method thereof |
| CN109903876B (en) * | 2017-03-10 | 2020-07-31 | 清华大学 | Radioactive waste resin cement curing slurry and preparation method thereof |
| CN107626717A (en) * | 2017-09-28 | 2018-01-26 | 重庆天志环保有限公司 | A kind of bitumen solidification technique of hazardous waste |
| CN108490905A (en) * | 2018-05-14 | 2018-09-04 | 镇江新区固废处置股份有限公司 | A kind of solidification of waste DCS control methods |
| CN111066094A (en) * | 2018-07-12 | 2020-04-24 | 原子能股份公司 | Waste ion exchange resin treatment method and device |
| CN111066094B (en) * | 2018-07-12 | 2023-12-12 | 原子能股份公司 | Method and device for treating waste ion exchange resin |
| CN110085342A (en) * | 2019-04-23 | 2019-08-02 | 中国核电工程有限公司 | The retired method of Spent Radioactive liquid storage tank |
| CN110648776A (en) * | 2019-06-12 | 2020-01-03 | 中国核电工程有限公司 | Method for solidifying radioactive waste and application thereof |
| CN110211721A (en) * | 2019-07-11 | 2019-09-06 | 中国工程物理研究院应用电子学研究所 | A kind of drying device and drying means for reactor core wastewater treatment based on microwave |
| CN110890165A (en) * | 2019-10-23 | 2020-03-17 | 江苏中海华核环保有限公司 | Combined treatment device and treatment method for radioactive waste resin |
| CN110890165B (en) * | 2019-10-23 | 2022-05-13 | 江苏中海华核环保有限公司 | Combined treatment device and treatment method for radioactive waste resin |
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