CN110444310A - A kind of radioiodine treatment of wastes produced method - Google Patents
A kind of radioiodine treatment of wastes produced method Download PDFInfo
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- CN110444310A CN110444310A CN201910643121.0A CN201910643121A CN110444310A CN 110444310 A CN110444310 A CN 110444310A CN 201910643121 A CN201910643121 A CN 201910643121A CN 110444310 A CN110444310 A CN 110444310A
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- radioiodine
- waste
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- wastes produced
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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
- G21F9/02—Treating gases
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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Abstract
The invention belongs to Radwastes treatment technical fields, are related to a kind of radioiodine treatment of wastes produced method.The processing method in turn includes the following steps: (1) reacting radioiodine waste with sodium hydroxide, obtain radioiodine waste conversion product powder；(2) it is ground after mixing 4A zeolite with radioiodine waste conversion product powder, the grinding of deionized water further progress, refinement, Homogenization Treatments is added after dry weighing, obtains moistening uniform mixture；(3) it will moisten after uniform mixture hydrolysis is evaporated and carry out heating sintering, obtain iodine sodalite solidified body.It, can technical process be simple, energy conservation and environmental protection, safe and reliable carry out radioiodine treatment of wastes produced using radioiodine treatment of wastes produced method of the invention.
Description
Technical field
The invention belongs to Radwastes treatment technical fields, are related to a kind of radioiodine treatment of wastes produced method.
Background technique
The fast-developing generation along with a large amount of nuclear wastes of nuclear energy, wherein radioiodine -129/131 etc. are usually with I-、
IO3 -、I2、IO-Or CH3The forms such as I evaporate, and pollute the environment, and influence human body health.
Nuclear industry development early stage, radioiodine is fixed by way of absorption, such as Fudan University Tang Lijuan et al. is adopted
The radioactive emission containing radioiodine -129/131 is adsorbed with deposited silver-colored silica gel.Although this method is for I2And CH3I's
Removal efficiency reaches 99.99% or more, but obtains the deposited silver-colored silica gel particle containing iodine because of the influence vulnerable to environment temperature and pH, from
And the stability of material is influenced, it is not able to satisfy the demand disposed for a long time.
Mainly there are sea disposal method, cement, plastics, bitumen solidification method etc. to the processing method of radioiodine at present.These
Although method to a certain extent can be disposed radioiodine, there are solidified body stability is poor, cause secondary pollution
The problems such as, therefore can not meet the needs of long-term disposition radioiodine.
Summary of the invention
The object of the present invention is to provide a kind of radioiodine treatment of wastes produced method, with can technical process be simple, energy conservation
Environmentally friendly, safe and reliable carry out radioiodine treatment of wastes produced.
In order to achieve this, the present invention provides a kind of radioiodine treatment of wastes produced method in the embodiment on basis,
The processing method in turn includes the following steps:
(1) radioiodine waste is reacted with sodium hydroxide, obtains radioiodine waste conversion product powder (3I2+6NaOH
=5NaI+NaIO3+3H2O)；
(2) by 4A zeolite (chemical formula Na12[Al12Si12O48]·27H2O) mixed with radioiodine waste conversion product powder
It is ground after conjunction, the grinding of deionized water further progress, refinement, Homogenization Treatments is added after dry weighing, obtained wet uniform
Mixture；
(3) it will moisten after uniform mixture hydrolysis is evaporated and carry out heating sintering, obtain iodine sodalite solidified body.
In a preferred embodiment, the present invention provides a kind of radioiodine treatment of wastes produced method, wherein step
(1) in, the mass ratio of radioiodine waste and sodium hydroxide is 70-80:20-30.
In a preferred embodiment, the present invention provides a kind of radioiodine treatment of wastes produced method, wherein step
(2) in, the mass ratio of 4A zeolite and radioiodine waste conversion product powder is 45-65:35-55.
In a preferred embodiment, the present invention provides a kind of radioiodine treatment of wastes produced method, wherein step
(2) in, the mass ratio of 4A zeolite, the mixture of radioiodine waste conversion product powder and deionized water is 1:10-1:5.
In a preferred embodiment, the present invention provides a kind of radioiodine treatment of wastes produced method, wherein step
(2) in, the average grain diameter for moistening solidfied material in uniform mixture is 1-5 μm.
In a preferred embodiment, the present invention provides a kind of radioiodine treatment of wastes produced method, wherein step
(3) in, hydrolyzing the temperature being evaporated is 200-250 DEG C, time 10-60min.
In a preferred embodiment, the present invention provides a kind of radioiodine treatment of wastes produced method, wherein step
(3) in, the program for the sintering that heats up is as follows: being first warming up to 400-450 DEG C of heat preservation 10-15h, then is warming up to 650-1050 DEG C of heat preservation
10-60min。
In a preferred embodiment, the present invention provides a kind of radioiodine treatment of wastes produced method, wherein step
(3) in, the program for the sintering that heats up is as follows: being first warming up to 400-450 DEG C of heat preservation 10-15h, then is warming up to 750-950 DEG C of heat preservation 10-
40min。
The beneficial effects of the present invention are, being capable of technical process using radioiodine treatment of wastes produced method of the invention
Simply, energy conservation and environmental protection, safe and reliable carry out radioiodine treatment of wastes produced.
Specific embodiment
Embodiment 1: radioiodine treatment of wastes produced (one)
Step carries out radioiodine treatment of wastes produced with the following method:
(1) by 280g radioiodine waste, (source is the gaseous state I emitted in nuclear waste2) anti-with 80g sodium hydroxide
It answers, obtains radioiodine waste conversion product powder.
(2) in colloid mill (Langfang City hat after the 4A zeolite of 45g being mixed with the radioiodine waste conversion product powder of 55g
Logical Machinery Co., Ltd., JF-130 type) in grinding, weigh after 80 DEG C of dry 12h, addition deionized water (solid-liquid mass ratio 1:
10) further progress grinding, refinement, Homogenization Treatments, obtaining moistening uniform mixture, (average grain diameter of solidfied material is 1 μ
m)。
(3) uniform mixture will be moistened in Muffle furnace (Tianjin Stettlen Instrument Ltd., MFLC-7/12P type)
Middle hydrolysis carries out heating sintering after being evaporated (temperature is 200 DEG C, time 60min), and iodine side's sodium is obtained after cooled to room temperature
Stone solidified body.The program being sintered that heats up is as follows: being first warming up to 400 DEG C of heat preservation 15h, then is warming up to 950 DEG C of heat preservation 10min.
It is tested through XRD, iodine sodalite solidified body object obtained is divided by main diffraction peak Na4Al3Si3O12Outside I, there is also few
The NaAlSi of amount2O6, bulk density 2.298g/cm3, (leaching rate shows to be wanted the leaching rate of radionuclide I under PCT standard
The percentage that the degree that the element of extraction is leached, i.e. element are leached；Leaching rate measuring method referring to Sakuragi T,
Nishimura T,Nasu Y,et al.Immobilization of radioactive iodine using AgI
vitrification technique for the TRU wastes disposal:evaluation of leaching
and surface properties[J].MRS Online Proceedings Library Archive,2008,1107.)
It is lower than 4.23 × 10 after 42 days-4g·m-2·d-1。
Embodiment 2: radioiodine treatment of wastes produced (two)
Step carries out radioiodine treatment of wastes produced with the following method:
(1) by 280g radioiodine waste, (source is the gaseous state I emitted in nuclear waste2) anti-with 120g sodium hydroxide
It answers, obtains radioiodine waste conversion product powder.
(2) in colloid mill (Langfang City hat after the 4A zeolite of 65g being mixed with the radioiodine waste conversion product powder of 35g
Logical Machinery Co., Ltd., JF-130 type) in grinding, weigh after 80 DEG C of dry 12h, addition deionized water (solid-liquid mass ratio 1:
5) further progress grinding, refinement, Homogenization Treatments obtain moistening uniform mixture (average grain diameter of solidfied material is 5 μm).
(3) uniform mixture will be moistened in Muffle furnace (Tianjin Stettlen Instrument Ltd., MFLC-7/12P type)
Middle hydrolysis carries out heating sintering after being evaporated (temperature is 250 DEG C, time 10min), and iodine side's sodium is obtained after cooled to room temperature
Stone solidified body.The program being sintered that heats up is as follows: being first warming up to 450 DEG C of heat preservation 10h, then is warming up to 750 DEG C of heat preservation 40min.
It is tested through XRD, iodine sodalite solidified body object obtained is divided by main diffraction peak Na4Al3Si3O12Outside I, there is also few
The NaAlSi of amount2O6, bulk density 1.968g/cm3, the leaching rate of radionuclide I is lower than after 42 days under PCT standard
5.56×10-2g·m-2·d-1。
Embodiment 3: radioiodine treatment of wastes produced (three)
Step carries out radioiodine treatment of wastes produced with the following method:
(1) by 320g radioiodine waste, (source is the gaseous state I emitted in nuclear waste2) anti-with 80g sodium hydroxide
It answers, obtains radioiodine waste conversion product powder.
(2) in colloid mill (Langfang City hat after the 4A zeolite of 50g being mixed with the radioiodine waste conversion product powder of 50g
Logical Machinery Co., Ltd., JF-130 type) in grinding, weigh after 80 DEG C of dry 12h, addition deionized water (solid-liquid mass ratio 1:
8) further progress grinding, refinement, Homogenization Treatments obtain moistening uniform mixture (average grain diameter of solidfied material is 3 μm).
(3) uniform mixture will be moistened in Muffle furnace (Tianjin Stettlen Instrument Ltd., MFLC-7/12P type)
Middle hydrolysis carries out heating sintering after being evaporated (temperature is 220 DEG C, time 30min), and iodine side's sodium is obtained after cooled to room temperature
Stone solidified body.The program being sintered that heats up is as follows: being first warming up to 420 DEG C of heat preservation 13h, then is warming up to 850 DEG C of heat preservation 25min.
It is tested through XRD, iodine sodalite crystal phase obtained is single, bulk density 2.354g/cm3, radioactivity under PCT standard
The leaching rate of nucleic I is lower than 1.78 × 10 after 42 days-4g·m-2·d-1。
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 (8)
1. a kind of radioiodine treatment of wastes produced method, which is characterized in that the processing method in turn includes the following steps:
(1) radioiodine waste is reacted with sodium hydroxide, obtains radioiodine waste conversion product powder；
(2) it is ground after mixing 4A zeolite with radioiodine waste conversion product powder, deionized water is added after dry weighing into one
Step ground, refined, Homogenization Treatments, obtain moistening uniform mixture；
(3) it will moisten after uniform mixture hydrolysis is evaporated and carry out heating sintering, obtain iodine sodalite solidified body.
2. processing method according to claim 1, it is characterised in that: in step (1), radioiodine waste and sodium hydroxide
Mass ratio be 70-80:20-30.
3. processing method according to claim 1, it is characterised in that: in step (2), 4A zeolite and radioiodine waste turn
The mass ratio of compound powder is 45-65:35-55.
4. processing method according to claim 1, it is characterised in that: in step (2), 4A zeolite, radioiodine waste turn
The mixture of compound powder and the mass ratio of deionized water are 1:10-1:5.
5. processing method according to claim 1, it is characterised in that: in step (2), moisten and solidify in uniform mixture
The average grain diameter of object is 1-5 μm.
6. processing method according to claim 1, it is characterised in that: in step (3), hydrolyzing the temperature being evaporated is 200-
250 DEG C, time 10-60min.
7. processing method according to claim 1, which is characterized in that in step (3), the program for the sintering that heats up is as follows: first
It is warming up to 400-450 DEG C of heat preservation 10-15h, then is warming up to 650-1050 DEG C of heat preservation 10-60min.
8. processing method according to claim 1, which is characterized in that in step (3), the program for the sintering that heats up is as follows: first
It is warming up to 400-450 DEG C of heat preservation 10-15h, then is warming up to 750-950 DEG C of heat preservation 10-40min.
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Cited By (6)
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|---|---|---|---|---|
| CN111161901A (en) * | 2020-01-03 | 2020-05-15 | 中国原子能科学研究院 | Method for treating radioactive iodine waste |
| CN111584113A (en) * | 2020-04-07 | 2020-08-25 | 西南科技大学 | Solidification treatment method of radioactive zeolite waste |
| CN111863304A (en) * | 2020-08-20 | 2020-10-30 | 中国原子能科学研究院 | Sodalite-based ceramic curing method for radioactive iodine waste |
| CN111863305A (en) * | 2020-08-20 | 2020-10-30 | 中国原子能科学研究院 | Method for curing radioactive iodine-containing silver-coated silica gel |
| CN111986828A (en) * | 2020-08-20 | 2020-11-24 | 中国原子能科学研究院 | Sodalite-based ceramic-glass dual curing method for radioactive iodine waste |
| CN112201382A (en) * | 2020-10-26 | 2021-01-08 | 西南科技大学 | Low-temperature curing treatment method for radioactive silica gel waste |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111161901A (en) * | 2020-01-03 | 2020-05-15 | 中国原子能科学研究院 | Method for treating radioactive iodine waste |
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| CN111584113A (en) * | 2020-04-07 | 2020-08-25 | 西南科技大学 | Solidification treatment method of radioactive zeolite waste |
| CN111584113B (en) * | 2020-04-07 | 2022-04-29 | 西南科技大学 | Solidification treatment method of radioactive zeolite waste |
| CN111863304A (en) * | 2020-08-20 | 2020-10-30 | 中国原子能科学研究院 | Sodalite-based ceramic curing method for radioactive iodine waste |
| CN111863305A (en) * | 2020-08-20 | 2020-10-30 | 中国原子能科学研究院 | Method for curing radioactive iodine-containing silver-coated silica gel |
| CN111986828A (en) * | 2020-08-20 | 2020-11-24 | 中国原子能科学研究院 | Sodalite-based ceramic-glass dual curing method for radioactive iodine waste |
| CN111863304B (en) * | 2020-08-20 | 2022-12-13 | 中国原子能科学研究院 | Sodalite-based ceramic curing method for radioactive iodine waste |
| CN111986828B (en) * | 2020-08-20 | 2022-12-13 | 中国原子能科学研究院 | Sodalite-based ceramic-glass dual curing method for radioactive iodine waste |
| CN112201382A (en) * | 2020-10-26 | 2021-01-08 | 西南科技大学 | Low-temperature curing treatment method for radioactive silica gel waste |
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