CN103723918A - Beryllium silicate glass containing Fe2O3 and method for processing radioactive waste liquid - Google Patents
Beryllium silicate glass containing Fe2O3 and method for processing radioactive waste liquid Download PDFInfo
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- CN103723918A CN103723918A CN201310515821.4A CN201310515821A CN103723918A CN 103723918 A CN103723918 A CN 103723918A CN 201310515821 A CN201310515821 A CN 201310515821A CN 103723918 A CN103723918 A CN 103723918A
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- glass
- beo
- roasting
- silicate glass
- beryllium silicate
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Abstract
The invention discloses beryllium silicate glass which comprises the components in percentage by mass as follows: a), 42%-49% of SiO2; b), 15%-20% of BeO; c), 11%-14% of Na2O; d), 5%-10% of Al2O3; e), 3%-6.5% of Fe2O3; f), at least one rare earth oxide, preferably, 3%-6.5% of La2O3, Nd2O3, Gd2O3, Pr2O3 or CeO2; g), at least one actinide oxide such as 3%-6.5% of UO2, ThO2, Am2O3, PuO2, CmO2 or NpO2; and h), 5%-8% of HfO2. The glass has very high stability for radiation, very good mechanical strength and very high chemical resistance, and can be used for sealing, storing and isolating the waste liquid under the condition that the size is reduced.
Description
Technical field
The present invention relates to a kind of beryllium silicate glass for nuclear reactor power plant sealing, preservation, isolation radioactive liquid waste.
Background technology
In the nuclear fuel regeneration equipment such as nuclear reactor, can produce the radioactive wastewater of medium-activity, mainly by bituminous grouting or cement solidification, process at present.But, adopt bituminous treatment to have several main drawbacks: stability reduces, and easily catches fire, and use range is limited, and physical strength is low.Adopt the expense of cement treated moderate, use simple, physical strength is good, stability is lasting.But cement solidification has two significant shortcomings: after coated, waste material volume doubles; The predicted life of the impact material that obtains.
In addition, now people also adopt glass capsulation radioactive liquid waste in research, because it has metamict, therefore compare conventional pitch and cement has obvious advantage.But because glass is metastable material, due to the existence of the alkaline elements such as sodium, cause glass stronger to the susceptibility of chemical erosion, cause glass basis to change, sealing stability is bad.For the deleterious effect of partial offset sodium, in silica glass, add boron, thereby the glass that is called " borosilicate glass " is provided.But the stability of borosilicate glass, physical strength and resistance to corrosion still can not meet the needs that people seal medium-activity waste liquid.
Summary of the invention
The invention discloses a kind of beryllium silicate glass, it has high stability, fabulous physical strength, high resistance to chemical attack to radiation, and this glass can well seal, preserve, isolate waste liquid in the situation that of volume-diminished.
Beryllium silicate glass of the present invention comprises the following composition that mass percent represents:
a)SiO
2：42-49
b)BeO：15-20
c)Na
2O：11-14
d)Al
2O
3：5-10
e)Fe
2O
3：3-6.5；
F) at least one rare earth oxide, is preferably, La
2o
3, Nd
2o
3, Gd
2o
3, Pr
2o
3, CeO
2: 3-6.5;
G) at least one actinide elements oxide compound, for example UO
2, ThO
2, Am
2o
3, PuO
2, CmO
2, NpO
2: 3-6.5;
h)HfO
2：5-8；
And the weight percent of the moiety of described glass meets following inequality further:
(1)SiO
2+Al
2O
3＜60％
(2)71％＜SiO
2+BeO+Na
2O＜85.5％
(3)BeO/Na
2O＞1.3。
In a preferred embodiment, in described glass, the content of BeO is 16～19%; More preferably 19%.
Fe in a preferred embodiment
2o
3content be 4～6%.
The invention also discloses a kind of method of processing the radioactive liquid waste of medium-activity, wherein, selectivity is added with to the described waste liquid roasting of roasting auxiliary agent, thereby acquisition product of roasting, then vitrifying auxiliary agent is added in described product of roasting, in cold-crucible, by described product of roasting and the fusing of described vitrifying auxiliary agent, obtain melted glass, then described melted glass is cooling, obtain thus above-mentioned beryllium silicate glass.
Glass of the present invention has composition and the scope of special composition, first has the SiO that conventional silicate glass includes
2, Na
2o, Al
2o
3, the traditional performance of assurance glass, on this basis, glass of the present invention has BeO, and Be element has well offseted the disadvantageous effect that in glass, Na element brings its chemical corrosivity, has greatly strengthened stability and the corrosion resistance of glass, this is still undiscovered in prior art, comprises HfO
2having strengthened significantly physical strength, is also that in prior art, not yet someone adopts; In addition, owing to thering is transition element oxide compound, rare earth oxide and actinide elements oxide compound, favourable enhancing its stability and resistance to corrosion.Different from the applicable sealing of borosilicate glass of the prior art highly active waste, beryllium silicate glass of the present invention starts from the radioactive liquid waste of sealing medium-activity.Adopt glass capsulation medium-activity waste material of the present invention, overcome the relevant defect of bituminous treatment or cement bond.In addition, glass of the present invention can easily obtain by roasting hereinafter described, the method for cold-crucible vitrifying type.
Embodiment
Below in conjunction with embodiment, describe beryllium silicate of the present invention in detail.
Beryllium silicate glass of the present invention comprises the following composition that mass percent represents:
a)SiO
2：42-49
b)BeO：15-20
c)Na
2O：11-14
d)Al
2O
3：5-10
E) oxide compound of at least one transition element, preferably Fe
2o
3, Cr
2o
3, MnO
2, TcO
2, RuO
2: 3-6.5;
F) at least one rare earth oxide, is preferably, La
2o
3, Nd
2o
3, Gd
2o
3, Pr
2o
3, CeO
2: 3-6.5;
G) at least one actinide elements oxide compound, for example UO
2, ThO
2, Am
2o
3, PuO
2, CmO
2, NpO
2: 3-6.5;
h)HfO
2：5-8；
And the weight percent of the moiety of described glass meets following inequality further:
(1)SiO
2+Al
2O
3＜60％
(2)71％＜SiO
2+BeO+Na
2O＜85.5％
(3)BeO/Na
2O＞1.3。
Embodiment 1:
Beryllium silicate glass of the present invention comprises the following composition that mass percent represents:
a)SiO
2：45
b)BeO：16
c)Na
2O：11
d)Al
2O
3：5
e)Fe
2O
3：4；
F) at least one rare earth oxide, is preferably, La
2o
3, Nd
2o
3, Gd
2o
3, Pr
2o
3, CeO
2: 6;
G) at least one actinide elements oxide compound, for example UO
2, ThO
2, Am
2o
3, PuO
2, CmO
2, NpO
2: 5;
h)HfO
2：8。
Embodiment 2
Beryllium silicate glass of the present invention comprises the following composition that mass percent represents:
a)SiO
2：46
b)BeO：16
c)Na
2O：11
d)Al
2O
3：5
E) oxide compound of at least one transition element, preferably Fe
2o
3, Cr
2o
3, MnO
2, TcO
2, RuO
2: 4;
f)La
2O
3：6；
G) at least one actinide elements oxide compound, for example UO
2, ThO
2, Am
2o
3, PuO
2, CmO
2, NpO
2: 5;
h)HfO
2：7。
Embodiment 3
Beryllium silicate glass of the present invention comprises the following composition that mass percent represents:
a)SiO
2：45
b)BeO：19
c)Na
2O：11
d)Al
2O
3：5
E) oxide compound of at least one transition element, preferably Fe
2o
3, Cr
2o
3, MnO
2, TcO
2, RuO
2: 3.5;
F) at least one rare earth oxide, is preferably, La
2o
3, Nd
2o
3, Gd
2o
3, Pr
2o
3, CeO
2: 3.5;
g)UO
2：6；
h)HfO
2：7。
The invention also discloses a kind of method of processing the radioactive liquid waste of medium-activity, wherein, selectivity is added with to the described waste liquid roasting of roasting auxiliary agent, thereby acquisition product of roasting, then vitrifying auxiliary agent is added in described product of roasting, in cold-crucible, by described product of roasting and the fusing of described vitrifying auxiliary agent, obtain melted glass, then described melted glass is cooling, obtain thus above-mentioned beryllium silicate glass.
Wherein said roasting auxiliary agent is selected from aluminum nitrate, iron nitrate, zirconium nitrate, rare earth nitrate or their mixture.Wherein said roasting auxiliary agent is the mixture of aluminum nitrate and iron nitrate.Described product of roasting and described vitrifying auxiliary agent be melted in 1,200 ℃ to 1,300 ℃, preferably at the temperature of 1,250 ℃, carry out.
First glass of the present invention have the SiO that conventional silicate glass includes
2, Na
2o, Al
2o
3guarantee the traditional performance of glass, on this basis, glass of the present invention has BeO, beryllium is compared boron can better offset the disadvantageous effect that in glass, Na element brings its chemical corrosivity, and can not produce ghost effect, greatly strengthen stability and the corrosion resistance of glass, this is still undiscovered in prior art.The HfO that glass comprises
2can strengthen its physical strength; In addition, owing to thering is transition element oxide compound, rare earth oxide and actinide elements oxide compound, its stability and resistance to corrosion have been strengthened.
From the above description of this invention, can obviously learn, the present invention can change with many forms.And these variations can not be considered to surpass technological thought of the present invention and scope.And, to those skilled in the art, within these apparent variant are all included in the scope of protection of the invention.
Claims (5)
1. a beryllium silicate glass that comprises Fe2O3, is characterized in that, comprises the following composition that mass percent represents:
a)SiO
2：42-49
b)BeO：15-20
c)Na
2O：11-14
d)Al
2O
3：5-10
e)Fe
2O
3：3-6.5；
F) at least one rare earth oxide, is preferably, La
2o
3, Nd
2o
3, Gd
2o
3, Pr
2o
3, CeO
2: 3-6.5;
G) at least one actinide elements oxide compound, for example UO
2, ThO
2, Am
2o
3, PuO
2, CmO
2, NpO
2: 3-6.5;
h)HfO
2：5-8；
And the weight percent of the moiety of described glass meets following inequality further:
(1)SiO
2+Al
2O
3＜60％
(2)71％＜SiO2+BeO+Na2O＜85.5％
(3)BeO/Na2O＞1.3。
2. glass as claimed in claim 1, is characterized in that, the content of BeO is 16～19%.
3. glass as claimed in claim 1, is characterized in that, the content of BeO is 19%.
4. glass as claimed in claim 1, is characterized in that, the content of Fe2O3 is 4～6%.
5. a method of processing the radioactive liquid waste of medium-activity, wherein, selectivity is added with to the described waste liquid roasting of roasting auxiliary agent, thereby acquisition product of roasting, then vitrifying auxiliary agent is added in described product of roasting, in cold-crucible, by described product of roasting and the fusing of described vitrifying auxiliary agent, obtain melted glass, then described melted glass is cooling, obtain thus the beryllium silicate glass described in above-mentioned any one claim.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310515821.4A CN103723918A (en) | 2013-10-26 | 2013-10-26 | Beryllium silicate glass containing Fe2O3 and method for processing radioactive waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310515821.4A CN103723918A (en) | 2013-10-26 | 2013-10-26 | Beryllium silicate glass containing Fe2O3 and method for processing radioactive waste liquid |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN103723918A true CN103723918A (en) | 2014-04-16 |
Family
ID=50448256
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201310515821.4A Pending CN103723918A (en) | 2013-10-26 | 2013-10-26 | Beryllium silicate glass containing Fe2O3 and method for processing radioactive waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103723918A (en) |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5580735A (en) * | 1978-12-07 | 1980-06-18 | Nippon Electric Glass Co Ltd | Solidification treating method for high level radioactive waste |
| JPH07225299A (en) * | 1994-02-10 | 1995-08-22 | Sanki Eng Co Ltd | Method for solidifying radioactive waste liquid containing sodium sulfate |
| JP2002221593A (en) * | 2001-01-25 | 2002-08-09 | Hitachi Ltd | Method for disposal of radioactive waste |
| CN1902138A (en) * | 2003-12-30 | 2007-01-24 | 康宁股份有限公司 | High strain point glasses |
| 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 |
-
2013
- 2013-10-26 CN CN201310515821.4A patent/CN103723918A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5580735A (en) * | 1978-12-07 | 1980-06-18 | Nippon Electric Glass Co Ltd | Solidification treating method for high level radioactive waste |
| JPH07225299A (en) * | 1994-02-10 | 1995-08-22 | Sanki Eng Co Ltd | Method for solidifying radioactive waste liquid containing sodium sulfate |
| JP2002221593A (en) * | 2001-01-25 | 2002-08-09 | Hitachi Ltd | Method for disposal of radioactive waste |
| CN1902138A (en) * | 2003-12-30 | 2007-01-24 | 康宁股份有限公司 | High strain point glasses |
| 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 |
Non-Patent Citations (3)
| Title |
|---|
| 干福熹等: "《光学玻璃 上册》", 30 November 1982, article "光学玻璃 上册", pages: 123 * |
| 王承遇等: "《玻璃材料手册》", 31 January 2008, article "玻璃材料手册", pages: 736-740 * |
| 西北轻工业学院主编: "《玻璃工艺学》", 31 January 2000, article "玻璃工艺学", pages: 193 - 203 * |
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| PB01 | Publication | ||
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Application publication date: 20140416 |