CN113345616A - Boron-containing radioactive waste liquid treatment method and system - Google Patents
Boron-containing radioactive waste liquid treatment method and system Download PDFInfo
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- CN113345616A CN113345616A CN202110685037.2A CN202110685037A CN113345616A CN 113345616 A CN113345616 A CN 113345616A CN 202110685037 A CN202110685037 A CN 202110685037A CN 113345616 A CN113345616 A CN 113345616A
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- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
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- 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
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Abstract
According to the embodiment of the invention, a boron-containing radioactive waste liquid treatment method and a system are provided, wherein the boron-containing radioactive waste liquid treatment method comprises the following steps: obtaining the content of boron element in the boron-containing radioactive waste liquid; preparing a curing agent, wherein the curing agent comprises boron, determining a desired range of the content of the boron in the curing agent according to the content of the boron in the boron-containing radioactive waste liquid and the desired range of the content of the boron in the cured product, and determining a formula of the curing agent based on the desired range of the content of the boron in the curing agent to prepare the curing agent according to the formula; mixing and heating the boron-containing radioactive waste liquid and the curing agent to form a molten substance; and cooling the molten substance to obtain the solidified product. According to the boron-containing radioactive waste liquid treatment method and system provided by the embodiment of the invention, the quality of the solidified product can be improved, and a relatively ideal treatment effect can be obtained.
Description
Technical Field
The invention relates to the technical field of chemical treatment, in particular to a method and a system for treating boron-containing radioactive waste liquid.
Background
With the rapid development of the nuclear industry, how to treat a large amount of radioactive waste generated in the nuclear industry is an urgent problem to be solved, and the solidification treatment is a method capable of treating the radioactive waste more safely and efficiently.
The solidification refers to the selection of a solidification matrix with higher stability to contain the nuclide for a long time, and common solidification methods include glass solidification, ceramic solidification, glass ceramic solidification, artificial rock solidification, various cement solidification and the like. The glass curing technology is mature, and the glass curing body has the advantages of low leaching rate, stable irradiation and the like, so that the glass curing technology becomes a hotspot of curing technology research.
The glass solidification is to mix the high level radioactive waste liquid and the glass substrate according to a certain proportion, then calcine, melt and cast at high temperature of 900-1200 ℃, and transform the mixture into a stable glass solidified body after annealing. Phosphate glass curing, in which phosphoric acid, phosphate or other phosphorus-containing substances are used as glass formers, and borosilicate glass curing, in which silica and boron trioxide are used as glass formers.
The research on glass solidification begins at the end of the 50 th 20 th century, phosphate glass solidification is studied more in the early stage, and then the phosphate glass solidified body is found to form crystals after being stored for a period of time, the transparency is lost, the leaching rate of radioactive nuclide is obviously increased, the phosphoric acid is strong in corrosivity, and a melter and a solidification tail gas pipeline need to use platinum as materials. The focus of research work has thus turned to borosilicate glass curing. The research result proves that the borosilicate glass is a more ideal high-level liquid waste curing substrate.
So far, glass solidification has been developed for 4 generations, and the 1 st generation melting process is an induction heating metal melting furnace, a one-step pot process. The pot-type process is characterized in that evaporation concentrated solution of high-level radioactive waste liquid and a glass forming agent are simultaneously and respectively added into a metal pot, the metal pot is heated by medium-frequency induction and is divided into a plurality of zones, the waste liquid is evaporated in the pot, is melted and clarified together with the glass forming agent, and finally, the melted glass is discharged from a freeze-thaw valve at the lower end.
The 2 nd generation melting process is a two-step process of a rotary calcining path and an induction heating metal melting furnace, which is a process developed on a tank type process, wherein in the 1 st step, high-level waste liquid is calcined in a rotary calcining furnace to form solid calcined substances, in the 2 nd step, the calcined substances and a glass forming agent are respectively added into a medium-frequency induction heating metal melting furnace, and are melted and cast into glass, and finally the glass is injected into a glass storage tank through a freeze-thaw valve. The process has the advantages of continuous production, large treatment capacity and complex process and short service life of the smelting furnace.
The 3 rd generation melting process is a joule heating ceramic furnace process, which was originally developed by the north-west laboratories of the pacific united states of america (electric melting furnace for short), and the joule heating ceramic furnace is heated by electrodes, and the furnace body is made of refractory ceramic materials. The high level radioactive waste liquid and the glass forming agent are respectively added into a melting furnace, and the high level radioactive waste liquid is evaporated in the melting furnace and is melted and cast into glass together with the glass forming agent. The melted glass is discharged from a bottom freeze-thaw valve or an overflow port in a batch or continuous manner. The joule heating ceramic furnace has the disadvantages of large process throughput, long service life (about 5 years), large volume of the furnace, difficulty in decommissioning, and possibility of deposition of precious metals at the bottom of the furnace, thereby affecting discharge.
The 4 th generation melting process is a cold crucible induction furnace process. The cold crucible is heated by high-frequency induction, the outer wall of the furnace body is provided with a water-cooling sleeve and a high-frequency induction coil, and refractory materials and electrodes are not needed for heating. High frequency (300-. The cold crucible can be used for melting waste metal, processing spent fuel cladding, burning high-chlorine high-sulfur waste plastic and waste resin and the like besides casting glass.
The cold crucible furnace has the advantages of high melting temperature (up to 1600-. Based on this, the cold crucible technology is a hot spot technology of intensive research in China and even all over the world.
In conventional pressurized water reactor nuclear power plants, boron is used for reactive chemical compensation control, which results in the production of large amounts of boron-containing radioactive waste. However, as mentioned above, borosilicate glass is used as a curing agent in the glass curing process, and the borosilicate glass also contains a large amount of boron, so that the quality of the final cured product is difficult to meet the desired standard.
Disclosure of Invention
In view of the above, the present invention has been made to provide a method and a system for solidification treatment of radioactive liquid waste containing boron which overcome the above problems or at least partially solve the above problems.
According to an aspect of the embodiments of the present invention, there is provided a method for solidifying a boron-containing radioactive waste liquid to obtain a solidified product, the method including the steps of: obtaining the content of boron element in the boron-containing radioactive waste liquid; preparing a curing agent, wherein the curing agent comprises boron, determining a desired range of the content of the boron in the curing agent according to the content of the boron in the boron-containing radioactive waste liquid and the desired range of the content of the boron in the cured product, and determining a formula of the curing agent based on the desired range of the content of the boron in the curing agent to prepare the curing agent according to the formula; mixing and heating the boron-containing radioactive waste liquid and the curing agent to form a molten substance; and cooling the molten substance to obtain the solidified product.
Optionally, the method further comprises: pretreating the boron-containing radioactive waste liquid to reduce the water content of the boron-containing radioactive waste liquid.
Alternatively, the desired range of the boron element content in the cured product is 10% to 20%.
Optionally, the obtaining the content of boron element in the boron-containing radioactive waste liquid includes: sampling the boron-containing radioactive waste liquid to obtain a sample to be detected; and measuring the content of the boron element in the sample to be detected by using a spectrophotometry method so as to obtain the content of the boron element in the boron-containing radioactive waste liquid.
Optionally, the method further comprises: obtaining the quality of the boron-containing radioactive waste liquid before mixing and heating the boron-containing radioactive waste liquid and the curing agent to form a molten state substance; and determining the mass of the curing agent according to the mass of the boron-containing radioactive waste liquid, and mixing the boron-containing radioactive waste liquid and the curing agent in a preset ratio.
Optionally, the mixing and heating the boron-containing radioactive waste liquid and the curing agent to form a molten substance comprises: and applying a magnetic field to the boron-containing radioactive waste liquid and the curing agent to enable the boron-containing radioactive waste liquid and the curing agent to generate electromagnetic reaction to generate induced electromotive force and form current, so that the boron-containing radioactive waste liquid and the curing agent are heated to form molten substances by utilizing heat generated by the current.
According to another aspect of the embodiments of the present invention, there is provided a boron-containing radioactive waste liquid treatment system for performing a solidification treatment on a boron-containing radioactive waste liquid to obtain a solidified product, the boron-containing radioactive waste liquid treatment system including: the measuring device is used for obtaining the content of boron in the boron-containing radioactive waste liquid; the formula determining module is used for determining the expected range of the content of the boron element in the curing agent according to the content of the boron element in the boron-containing radioactive waste liquid obtained by the measuring device and the expected range of the content of the boron element in the cured product, and determining the formula of the curing agent based on the expected range of the content of the boron element in the curing agent; the smelting device is used for preparing the curing agent according to the formula; a reaction vessel for providing a reaction space for the boron-containing radioactive waste liquid and the curing agent; a heating device for heating the boron-containing radioactive waste liquid and the curing agent in the reaction vessel to form a molten substance; and a cooling device, which is communicated with the reaction vessel and is used for cooling the molten state substance to obtain a solidified product.
Optionally, the boron-containing radioactive waste liquid treatment system further comprises: and the pretreatment device is communicated with the reaction vessel and is used for pretreating the boron-containing radioactive waste liquid so as to reduce the water content of the boron-containing radioactive waste liquid.
Optionally, the reaction vessel comprises a side wall made of a metallic material; the heating device comprises a coil wound outside the side wall, and when the heating device works, current is introduced into the coil, so that the coil and the side wall generate electromagnetic induction, and a magnetic field environment is formed inside the reaction vessel to heat the boron-containing radioactive waste liquid and the curing agent.
Optionally, the side wall comprises a plurality of metal tubes insulated from each other, and a coolant is disposed in the metal tubes to cool the side wall and condense a part of the molten material on a surface of the side wall close to one side of the interior of the reaction vessel, so as to prevent the molten material from corroding the side wall.
According to the boron-containing radioactive waste liquid treatment method and system provided by the embodiment of the invention, the quality of the solidified product can be improved, and a relatively ideal treatment effect can be obtained.
Drawings
FIG. 1 is a schematic view of a method for solidifying a radioactive liquid waste containing boron according to an embodiment of the present invention;
FIG. 2 is a schematic view of a method for solidifying boron-containing radioactive waste liquid according to another embodiment of the present invention;
FIG. 3 is a schematic view of a boron-containing radioactive waste treatment system according to one embodiment of the present invention;
FIG. 4 is a schematic view of a boron-containing radioactive waste treatment system according to another embodiment of the present invention;
fig. 5 is a schematic view of a reaction vessel and a heating device of a boron-containing radioactive waste treatment system according to an embodiment of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the technical solutions of the present invention will be described clearly and completely with reference to the accompanying drawings of the embodiments of the present invention. It should be apparent that the described embodiment is one embodiment of the invention, and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the described embodiments of the invention without any inventive step, are within the scope of protection of the invention.
Unless defined otherwise, technical or scientific terms used herein shall have the ordinary meaning as understood by one of ordinary skill in the art to which this invention belongs.
According to an embodiment of the present invention, there is provided a method for treating a boron-containing radioactive waste liquid, referring to fig. 1, including:
step S102: obtaining the content of boron element in the boron-containing radioactive waste liquid;
step S104: preparing a curing agent, wherein the curing agent comprises boron, determining a desired range of the content of the boron in the curing agent according to the content of the boron in the boron-containing radioactive waste liquid and the desired range of the content of the boron in the cured product, and determining a formula of the curing agent based on the desired range of the content of the boron in the curing agent to prepare the curing agent according to the formula;
step S106: mixing and heating the boron-containing radioactive waste liquid and the curing agent to form a molten substance;
step S108: and cooling the molten substance to obtain the solidified product.
In step S104, a suitable curing agent needs to be prepared to perform a curing treatment on the boron-containing radioactive waste liquid. The curing agent comprises boron element, for example, the curing agent can comprise borosilicate glass, so as to carry out glass curing treatment on the boron-containing radioactive waste liquid. It can be understood that when the conventional borosilicate glass is used for curing other radioactive substances, the content of the boron element in the cured product can be ensured to be within a desired range only by controlling the dosage ratio of the curing agent to the radioactive substances. However, when treating the boron-containing radioactive waste liquid, the curing treatment using a conventional curing agent containing borosilicate glass may cause the content of boron in the cured product to be excessive, resulting in difficulty in the quality of the cured product to be expected.
In order to enable the content of the boron element in the cured product to be within a desired range, in this embodiment, the content of the boron element in the boron-containing radioactive waste liquid is obtained, then the desired range of the content of the boron element in the curing agent is determined according to the content of the boron element in the boron-containing radioactive waste liquid and the desired range of the content of the boron element in the cured product, and further, the formula of the curing agent is determined based on the desired range of the content of the boron element in the curing agent.
It can be understood that the curing agent contains various other elements besides boron, and in order to make the content of boron in the curing agent within a desired range, the content of boron needs to be adjusted not only on the basis of the conventional curing agent, but also correspondingly, the content of various other elements needs to be adjusted to ensure the stability of the structure of the curing agent. Still taking borosilicate glass as an example, borosilicate glass usually contains a certain proportion of substances such as boron oxide, silica, sodium oxide and alumina, and when the content of boron oxide is controlled to be within a predetermined range, the content of substances such as silica, sodium oxide and alumina needs to be determined accordingly, so that the proportion between the substances can ensure the stability of borosilicate glass, that is, determining the formula of the curing agent actually determines the content ratio between the substances in the curing agent.
After the formula of the curing agent is determined, the curing agent can be prepared according to the formula, in some embodiments, the curing agent can be obtained by melting the raw materials according to the proportion in the formula, in some embodiments, the curing agent can be obtained by performing secondary processing on the basis of the existing curing agent, and a person skilled in the art can select a suitable mode to prepare the curing agent, which is not specifically limited herein.
After the preparation of the curing agent is completed, the boron-containing radioactive waste liquid and the curing agent are mixed and heated to a molten state, and then the molten state substance is cooled to obtain a cured product.
According to the method for curing the boron-containing radioactive waste liquid, disclosed by the embodiment of the invention, the content of boron in the cured product can be ensured to be within an expected range, the excessive content of boron in the cured product caused by the fact that the boron-containing radioactive waste liquid contains the boron per se is avoided, and a better curing treatment effect is obtained.
In some embodiments, referring to fig. 2, a method for solidification treatment of boron-containing radioactive waste liquid according to another embodiment of the present invention may include:
step S202: pretreating the boron-containing radioactive waste liquid to reduce the water content of the boron-containing radioactive waste liquid;
step S204: obtaining the content of boron element in the boron-containing radioactive waste liquid;
step S206: preparing a curing agent, wherein the curing agent comprises boron, determining a desired range of the content of the boron in the curing agent according to the content of the boron in the boron-containing radioactive waste liquid and the desired range of the content of the boron in the cured product, and determining a formula of the curing agent based on the desired range of the content of the boron in the curing agent to prepare the curing agent according to the formula;
step S208: mixing and heating the boron-containing radioactive waste liquid and the curing agent to form a molten substance;
step S210: and cooling the molten substance to obtain the solidified product.
In this embodiment, before obtaining the content of boron in the boron-containing radioactive waste liquid and mixing and heating the boron-containing radioactive waste liquid and the curing agent, the boron-containing radioactive waste liquid is pretreated to reduce the water content of the boron-containing radioactive waste liquid, so that the boron-containing radioactive waste liquid is concentrated, thereby improving the efficiency of the curing treatment and further ensuring the quality of the cured product.
In some embodiments, the desired range of elemental boron content in the cured product is 10% to 20%.
In some embodiments, obtaining the boron content of the boron-containing radioactive waste liquid comprises: sampling the boron-containing radioactive waste liquid to obtain a sample to be detected; and measuring the content of the boron element in the sample to be detected by using a spectrophotometry method so as to obtain the content of the boron element in the boron-containing radioactive waste liquid. The measurement of the boron content can be performed by those skilled in the art using spectrophotometric methods, such as curcumin spectrophotometry, azomethine-H spectrophotometry, etc., and will not be described herein.
In some embodiments, the method further comprises: obtaining the quality of the boron-containing radioactive waste liquid before mixing and heating the boron-containing radioactive waste liquid and a curing agent to form a molten substance; and determining the quality of the curing agent according to the quality of the boron-containing radioactive waste liquid, and mixing the boron-containing radioactive waste liquid and the curing agent in a preset ratio. Namely, the boron-containing radioactive waste liquid and the curing agent are mixed and heated according to a preset proportion, so that the content ratio of each element in the cured product is further ensured to be in a preset range, and the curing treatment effect is improved.
In some embodiments, mixing and heating the boron-containing radioactive waste liquid with the solidifying agent to form a molten mass comprises: and applying a magnetic field to the boron-containing radioactive waste liquid and the curing agent to enable the boron-containing radioactive waste liquid and the curing agent to generate electromagnetic reaction to generate induced electromotive force and form current, so that the boron-containing radioactive waste liquid and the curing agent are heated to form molten substances by utilizing heat generated by the current. Specifically, in such an embodiment, the reaction vessel may be a reaction vessel having an electromagnetic heating function, such as an electromagnetic furnace, a cold crucible, or the like, and heating by electromagnetic induction is more environmentally friendly and contributes to energy saving.
According to an embodiment of the present invention, there is also provided a boron-containing radioactive waste liquid treatment system for performing solidification treatment on boron-containing radioactive waste liquid, and referring to fig. 3 to 5, the system includes: the measuring device 10 is used for obtaining the content of boron in the radioactive boron-containing waste liquid; the formula determining module 20 is used for determining the expected range of the boron element content in the curing agent according to the boron element content in the boron-containing radioactive waste liquid obtained by the measuring device 10 and the expected range of the boron element content in the cured product, and determining the formula of the curing agent based on the expected range of the boron element content in the curing agent; a smelting device 30 for preparing a curing agent according to a formula; a reaction vessel 40 for providing a reaction space for the boron-containing radioactive waste liquid and the curing agent; a heating device 50 for heating the boron-containing radioactive waste liquid and the curing agent in the reaction vessel 40 to form a molten substance; and a cooling device 60 communicating with the reaction vessel 50 for cooling the molten mass to obtain a solidified product.
The boron-containing radioactive waste liquid treatment system according to the embodiment of the invention is provided with the measuring device 10 to obtain the content of boron in the boron-containing radioactive waste liquid, then the formula determining module 20 is used to determine the expected range of the content of boron in the curing agent according to the content of boron in the boron-containing radioactive waste liquid and the expected range of the content of boron in the cured product, determine the formula of the curing agent based on the expected range of the content of boron in the curing agent, and then the melting device 30 is used to prepare the curing agent according to the formula, so that the content of boron in the finally obtained cured product can be ensured to be in the expected range, and the quality of the cured product is improved.
In some embodiments, referring to fig. 4, the boron-containing radioactive waste treatment system further comprises: and the pretreatment device 70 is communicated with the reaction vessel 40, and the pretreatment device 70 is used for pretreating the boron-containing radioactive waste liquid so as to reduce the water content of the boron-containing radioactive waste liquid. The pre-treatment device may use evaporation to reduce the water content of the boron-containing radioactive waste, for example, the pre-treatment device 70 may be a heat pump evaporator.
In this embodiment, the water content in the radioactive boron-containing waste liquid is reduced by the pretreatment device 70 to concentrate the radioactive boron-containing waste liquid, thereby improving the efficiency of the solidification treatment.
In some embodiments, referring to fig. 5, the reaction vessel 40 may include a sidewall 41 made of a metal material; the heating device 50 includes a coil 51 wound outside the sidewall 41, and when the heating device 50 works, current is supplied to the coil 51, so that the coil 51 and the sidewall 41 generate electromagnetic induction, and a magnetic field environment is formed inside the reaction vessel 40 to heat the boron-containing radioactive waste liquid and the curing agent.
It can be understood that, since the coil 51 is wound on the outer side of the metal sidewall 41, when current is introduced into the coil 51, electromagnetic induction will occur between the coil 51 and the sidewall 41, a magnetic field is generated inside the reaction vessel 40, and the specific strength of the magnetic field can be adjusted by the winding manner of the coil 51, the current strength and the frequency in the coil 51, and those skilled in the art can set the magnetic field according to the temperature requirement and the like of the actual reaction, and in some other embodiments, the coil 51 can be optionally wound on other parts of the reaction vessel 40 to achieve similar effects, which is not described herein again.
The specific effect of heating the boron-containing radioactive waste liquid and the curing agent by using the magnetic field can be referred to the related contents, and will not be described in detail herein.
In some embodiments, still referring to FIG. 5, the sidewall 41 includes a plurality of metal tubes 411 that are insulated from one another, and a coolant is disposed within the metal tubes 411 to cool the sidewall 41 and cause a portion of the molten material to condense on the surface of the sidewall 41 on the side thereof adjacent the interior of the reaction vessel 40 to prevent the molten material from corroding the sidewall 41.
It will be appreciated that in such an embodiment, the magnetic field generated within the reaction vessel heats the boron-containing radioactive waste liquid and the curing agent, i.e. the interior of the reaction vessel will generate a high temperature, while the side wall 41 of the reaction vessel will be kept at a relatively low temperature by the coolant, which effectively extends the service life of the reaction vessel 40. Meanwhile, molten substances generated by the radioactive resin and the curing agent have strong corrosivity, the temperature of the side wall 41 is low, the molten substances are partially condensed on the side wall 41, the corrosivity of the condensed molten substances is greatly reduced, a protective layer is formed, the side wall 41 is prevented from being corroded by the molten substances, and the service life of the reaction vessel 40 is prolonged.
Further, in such an embodiment, since the plurality of metal tubes 411 are insulated from each other, when the coil 51 is wound outside the side wall 41, it is equivalent to winding outside the plurality of metal tubes 411, and current in opposite directions will be generated in two adjacent metal tubes 411, further creating a magnetic field enhancement effect, so that the magnetic field inside the reaction vessel 40 is enhanced, thereby improving the heating efficiency.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.
Claims (10)
1. A method for solidifying boron-containing radioactive waste liquid is used for solidifying the boron-containing radioactive waste liquid to obtain a solidified product, and comprises the following steps:
obtaining the content of boron element in the boron-containing radioactive waste liquid;
preparing a curing agent, wherein the curing agent comprises boron, determining a desired range of the content of the boron in the curing agent according to the content of the boron in the boron-containing radioactive waste liquid and the desired range of the content of the boron in the cured product, and determining a formula of the curing agent based on the desired range of the content of the boron in the curing agent to prepare the curing agent according to the formula;
mixing and heating the boron-containing radioactive waste liquid and the curing agent to form a molten substance;
and cooling the molten substance to obtain the solidified product.
2. The method of claim 1, further comprising:
pretreating the boron-containing radioactive waste liquid to reduce the water content of the boron-containing radioactive waste liquid.
3. The method according to claim 1 or 2, wherein the desired range of boron element content in the cured product is 10% -20%.
4. The method of any one of claims 1-3, wherein said obtaining the elemental boron content in said boron-containing radioactive spent liquor comprises:
sampling the boron-containing radioactive waste liquid to obtain a sample to be detected;
and measuring the content of the boron element in the sample to be detected by using a spectrophotometry method so as to obtain the content of the boron element in the boron-containing radioactive waste liquid.
5. The method of any of claims 1-4, further comprising:
obtaining the quality of the boron-containing radioactive waste liquid before mixing and heating the boron-containing radioactive waste liquid and the curing agent to form a molten state substance;
and determining the mass of the curing agent according to the mass of the boron-containing radioactive waste liquid, and mixing the boron-containing radioactive waste liquid and the curing agent in a preset ratio.
6. The method of any one of claims 1-5, wherein the mixing and heating the boron-containing radioactive spent liquor with the solidifying agent to form a molten mass comprises:
and applying a magnetic field to the boron-containing radioactive waste liquid and the curing agent to enable the boron-containing radioactive waste liquid and the curing agent to generate electromagnetic reaction to generate induced electromotive force and form current, so that the boron-containing radioactive waste liquid and the curing agent are heated to form molten substances by utilizing heat generated by the current.
7. A boron-containing radioactive waste liquid treatment system for performing solidification treatment on boron-containing radioactive waste liquid to obtain solidified products, the boron-containing radioactive waste liquid treatment system comprising:
the measuring device is used for obtaining the content of boron in the boron-containing radioactive waste liquid;
the formula determining module is used for determining the expected range of the content of the boron element in the curing agent according to the content of the boron element in the boron-containing radioactive waste liquid obtained by the measuring device and the expected range of the content of the boron element in the cured product, and determining the formula of the curing agent based on the expected range of the content of the boron element in the curing agent;
the smelting device is used for preparing the curing agent according to the formula;
a reaction vessel for providing a reaction space for the boron-containing radioactive waste liquid and the curing agent;
a heating device for heating the boron-containing radioactive waste liquid and the curing agent in the reaction vessel to form a molten substance; and
and the cooling device is communicated with the reaction vessel and is used for cooling the molten state substance to obtain a solidified product.
8. The boron-containing radioactive liquid waste treatment system according to claim 7, further comprising:
and the pretreatment device is communicated with the reaction vessel and is used for pretreating the boron-containing radioactive waste liquid so as to reduce the water content of the boron-containing radioactive waste liquid.
9. The boron-containing radioactive liquid waste treatment system according to claim 7 or 8, wherein the reaction vessel comprises a side wall made of a metallic material;
the heating device comprises a coil wound outside the side wall, and when the heating device works, current is introduced into the coil, so that the coil and the side wall generate electromagnetic induction, and a magnetic field environment is formed inside the reaction vessel to heat the boron-containing radioactive waste liquid and the curing agent.
10. The boron-containing radioactive liquid waste treatment system according to claim 9, wherein the sidewall comprises a plurality of metal tubes insulated from each other, and a coolant is disposed in the metal tubes to cool the sidewall and condense a portion of the molten material on a surface of the sidewall adjacent to a side of the interior of the reaction vessel to prevent the molten material from corroding the sidewall.
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Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5082603A (en) * | 1990-03-15 | 1992-01-21 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Method of treatment of high-level radioactive waste |
| CN102272859A (en) * | 2008-12-30 | 2011-12-07 | 阿雷瓦核废料回收公司 | Alumino-borosilicate glass for confining radioactive liquid effluents, and method for processing radioactive effluents |
| CN103886926A (en) * | 2012-12-21 | 2014-06-25 | 中核核电运行管理有限公司 | Radioactive concentrated liquor solidifying formula |
| CN105741899A (en) * | 2016-02-25 | 2016-07-06 | 中国核动力研究设计院 | Solidification treatment additive, solidification formula and solidification process for radioactive boron-containing waste liquor |
| CN109994240A (en) * | 2017-12-31 | 2019-07-09 | 中国人民解放军63653部队 | The method for reducing radionuclide contamination sand glass solidification fusion temperature |
| CN110092588A (en) * | 2019-05-13 | 2019-08-06 | 中国建筑材料科学研究总院有限公司 | A kind of borosilicate glass ceramic solidification substrate and its preparation method and application |
| CN112624608A (en) * | 2020-12-18 | 2021-04-09 | 中国建筑材料科学研究总院有限公司 | Borosilicate glass curing substrate and preparation method and application thereof |
-
2021
- 2021-06-21 CN CN202110685037.2A patent/CN113345616B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5082603A (en) * | 1990-03-15 | 1992-01-21 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Method of treatment of high-level radioactive waste |
| CN102272859A (en) * | 2008-12-30 | 2011-12-07 | 阿雷瓦核废料回收公司 | Alumino-borosilicate glass for confining radioactive liquid effluents, and method for processing radioactive effluents |
| CN103886926A (en) * | 2012-12-21 | 2014-06-25 | 中核核电运行管理有限公司 | Radioactive concentrated liquor solidifying formula |
| CN105741899A (en) * | 2016-02-25 | 2016-07-06 | 中国核动力研究设计院 | Solidification treatment additive, solidification formula and solidification process for radioactive boron-containing waste liquor |
| CN109994240A (en) * | 2017-12-31 | 2019-07-09 | 中国人民解放军63653部队 | The method for reducing radionuclide contamination sand glass solidification fusion temperature |
| CN110092588A (en) * | 2019-05-13 | 2019-08-06 | 中国建筑材料科学研究总院有限公司 | A kind of borosilicate glass ceramic solidification substrate and its preparation method and application |
| CN112624608A (en) * | 2020-12-18 | 2021-04-09 | 中国建筑材料科学研究总院有限公司 | Borosilicate glass curing substrate and preparation method and application thereof |
Non-Patent Citations (3)
| Title |
|---|
| JIAWEI SHENG: "Vitrification of Borate Waste Generated by Nuclear Power Plants", 《NUCKEAR TECHNOLOGY》 * |
| 李平广，等: "氧化硼对硅酸盐玻璃固化体结构及抗浸出性能的影响", 《材料科学与工程学报》 * |
| 罗上庚: "玻璃固化国际现状及发展前景", 《硅酸盐通报》 * |
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