GB2302201A - Method for converting high level radioactive waste into glass using fly ash - Google Patents

Method for converting high level radioactive waste into glass using fly ash Download PDF

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Publication number
GB2302201A
GB2302201A GB9517686A GB9517686A GB2302201A GB 2302201 A GB2302201 A GB 2302201A GB 9517686 A GB9517686 A GB 9517686A GB 9517686 A GB9517686 A GB 9517686A GB 2302201 A GB2302201 A GB 2302201A
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GB
United Kingdom
Prior art keywords
fly ash
radioactive waste
high level
level radioactive
metal oxide
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
GB9517686A
Other versions
GB2302201B (en
GB9517686D0 (en
Inventor
Gwan-Sik Jeon
Jin-Myung Sin
Hyun-Soo Park
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Korea Atomic Energy Research Institute KAERI
Korea Electric Power Corp
Original Assignee
Korea Atomic Energy Research Institute KAERI
Korea Electric Power Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
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Publication date
Application filed by Korea Atomic Energy Research Institute KAERI, Korea Electric Power Corp filed Critical Korea Atomic Energy Research Institute KAERI
Publication of GB9517686D0 publication Critical patent/GB9517686D0/en
Publication of GB2302201A publication Critical patent/GB2302201A/en
Application granted granted Critical
Publication of GB2302201B publication Critical patent/GB2302201B/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/301Processing by fixation in stable solid media
    • G21F9/302Processing by fixation in stable solid media in an inorganic matrix
    • G21F9/305Glass or glass like matrix
    • CCHEMISTRY; METALLURGY
    • C03GLASS; MINERAL OR SLAG WOOL
    • C03CCHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
    • C03C1/00Ingredients generally applicable to manufacture of glasses, glazes, or vitreous enamels
    • C03C1/002Use of waste materials, e.g. slags
    • CCHEMISTRY; METALLURGY
    • C03GLASS; MINERAL OR SLAG WOOL
    • C03CCHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
    • C03C14/00Glass compositions containing a non-glass component, e.g. compositions containing fibres, filaments, whiskers, platelets, or the like, dispersed in a glass matrix
    • CCHEMISTRY; METALLURGY
    • C03GLASS; MINERAL OR SLAG WOOL
    • C03CCHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
    • C03C3/00Glass compositions
    • C03C3/04Glass compositions containing silica
    • C03C3/076Glass compositions containing silica with 40% to 90% silica, by weight
    • C03C3/089Glass compositions containing silica with 40% to 90% silica, by weight containing boron

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Organic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Inorganic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Ceramic Engineering (AREA)
  • Dispersion Chemistry (AREA)
  • Processing Of Solid Wastes (AREA)
  • Glass Compositions (AREA)

Abstract

The method includes the steps of: purifying fly ash generated from coal-fired steam power plants; mixing fly ash with SiO 2 or sand, B 2 O 3 or Na 2 B 4 O 7 or H 3 BO 3 , NaNO 3 or Na 2 CO 3 , and high level radioactive waste in an amount based on oxides of: 10-65wt% of fly ash, 0-45wt% of SiO 2 , 10-17wt% of B 2 O 3 , 10-19wt% of Na 2 O, and 5-30wt% of high level radioactive waste; and heating and melting the mixture so as to stabilize the waste, whereby high level radioactive waste is converted into borosilicate glass form by adding fly ash in an amount of up to 65% by weight.

Description

METHOD FOR CONVERTING HIGH LEVEL RADIOACTIVE WASTE INTO GLASS USING FLY ASH DESCRIPTION The present invention relates to a method for converting high level radioactive waste into solidified glass form using fly ash generated from coal-fired steam power plants.
The term "high level radioactive waste" refers to nuclear fuel burnt at nuclear power plants or to high level radioactive waste generated by wet or dry processing of used fuel. In treating such high level radioactive waste, borosilicate glass has advantages compared with other glasses because its chemical durability and resistance to radioactivity are superior and because it can be easily formed into glass within a wide chemical composition range.
Conventional raw materials used in glass making to vitrify high level radioactive waste include clay, zeolite, glass wool, basalt, diatomite, and the like.
The use of fly ash in such glass making processes provides many advantages because it contains silica, which is a basic component of borosilicate glass, and it also contains a large amount of alumina, which has a strongly beneficial effect on leach rate.
Moreover, fly ash consists of finely divided particles of between 1 and 150 ssm, which can be collected from ash contained in flue gas and are produced as a byproduct in an amount of 15-458 of the raw coal, when fine powder coal is burned at coal-fired steam power plants.
Fly ash is a visible pollutant and, therefore, is often the subject of complaints from nearby residents.
Currently, in most coal-fired steam power plants, fly ash is collected and stored in ash ponds, after being formed into slurry. In this state, it is known that water and soil pollution caused by leaching of certain chemical elements in the fly ash can present serious problems.
The present invention is intended to overcome some of the aforementioned problems.
It is an object of the present invention, therefore, to provide a method for converting high level radioactive waste into solidified glass form using fly ash generated from coal-fired steam power plants. It has also been found that the use of fly ash as a glass making material can cut down on material costs and that the solidified glass obtained thereby has good leach resistance.
In achieving the above object, the method according to the present invention comprises the steps of: purifying fly ash generated from coal-fired steam power plants; mixing fly ash with SiO2 or sand, B203, (or Na2B4Q, H3BO3, Na2CO3 (these are selected properly), and high level radioactive waste (nuclear fuel burnt at a nuclear power plant or high level radioactive waste generated from wet or dry processing of used fuel) in an amount based on oxides of: 10-65wt% of fly ash, 0-45wt% of SiO2, 10-17wtk of B2O3 10-19wt% of Na2O, and 5-30wt% of high level radioactive waste; and heating and melting the mixture so as to stabilize the waste, whereby high level radioactive waste is converted into borosilicate glass form by adding fly ash in an amount of up to 65% by weight.
In the present invention, it is has been found that fly ash, which is a by-product of coal-fired steam power plants, can be added in amounts of up to 65% by weight as a stabilizing material for high level radioactive waste.
An example of a typical fly ash composition is: 60.Owt% of SiO2, 24.2wt% of Al2O3, 5.68wt% of Fe2O3, and 1.34wt% of CaO. With such a composition, it was found that borosilicate glass can be manufactured by adding the fly ash in amounts of up to 65k by weight and, thus, that the costs of raw materials used in manufacturing the solidified glass can be reduced.Leach tests on the resultant glasses were conducted and test results showed that their leach rates were good. (Na: 4.250-7.943x10-4 g/cm2 per day, Cs: 1.609-2.064x10-4 g/cm2 per day, B: 8.490x10-4-1. 520x10-3 g/cm2 per day, Si: 2.169-4.375 x 10-4 g/cm2 per day, Al: 5.950 x 10-5 -1.313-4 g/cm2 per day, U: 7.326-9.826x10-6g/cm2 per day).
In the present invention, fly ash, which contains large amounts of silica and alumina is mixed with SiO2, B203, Na2O and high level radioactive waste, and then this mixture is heated and melted to form a solidified glass with the waste stabilized therein.
The term "fly ash" as used in the present invention refers to waste generated during the coal combustion process at coal-fired steam power plants and includes the following materials.
1. Fly ash produced in coal-fired steam power plants using anthracite and bituminous coal 2. Fly ash obtained by purifying the fly ash in 1.
The present invention will now be described by way of the following illustrative example.
Fly ash, SiO2, B203, NaNO3 and waste (Table 1) were mixed and melted to convert the high level radioactive waste into a glass form having the composition shown in Table 2. Then, leach tests were carried out and the results are shown in Table 3.
According to the invention as described above, therefore, fly ash can be converted from industrial waste into a usable resource and such reutilization can be achieved both economically and effectively.
Table 1. Composition of simulated high level radioactive wastes (burn up : 35,000 MWDIMTU, cooling time : 10 years)
Element Oxides form wt% Reagents used 5 Sr SrO 0.085 Sr(NO3)2 Zr ZrO@ 0.457 ZrO2 Mo MoO3 0.381 MoO3 Ru RuO2 0.322 RuO2 Pd PdO 0.139 PdO Cd CdO 0.011 CdO Te TeO 0.049 TeO Cs Cs@O 0.233 CsNO3 10 Ba BaO 0.178 BaO La La2O3 0.127 La2O3 Ce CeO2 0.267 Ce(NO3)3 6H2O Nd Nd2O3 0.432 Nd2O3 Sm Sm2O3 0.086 Sm2O3 Eu Eu2O3 0.014 Eu2O3 Gd Gd2O3 0.011 Gd2O3 Y Y2O3 0.054 Y2O3 15 Rb Rb2O3 0.042 RbNO3 Rh Rh2O3 0.050 Rh2O3 Actinide U U3O8 97.134 UO2 Total 100.0 Table 2. Composition of solidified waste glass
Composition wt% Fly ash l l0-65 SiO2 0 - 45 B2O3 10 - 17 Na:0 10 - 19 Waste 5 - 30 Table 3. Leach rate of solidified waste glass
Na Cs B Si Al U 4.250x10-4 1.609x10-4 8.490x10-4 2.169x10-4 5.950x10-5 7.326x10-6 # # # # # # 7.943x10-4 2.064x10-4 1.520x10-3 4.375x10-4 1.313x10-4 9.826x10-6

Claims (14)

1. A method for converting high level radioactive waste into borosilicate glass form using fly ash, comprising the steps of: purifying fly ash generated from coal-fired steam power plants; mixing said purified fly ash with SiO2, B203 or Na2CO3 and with high level radioactive waste in an amount based on oxides of: 10-65wt of fly ash, 0-45wt% of SiO2, 10-1?wt% of B203, 10-19wt% of Na2O, and 5-30wt% of said high level radioactive waste; and heating and melting said mixture so as to stabilize the waste, whereby high level radioactive waste is converted into borosilicate glass form by adding fly ash in an amount of up to 65% by weight.
2. A method as claimed in claim 1, wherein as an additive to said fly ash, SiO2 or sand is selectively added depending on circumstances.
3. A method as claimed in claim 1, wherein as an additive to said fly ash, B203 or H3BO3 is selectively added depending on circumstances.
4. A method as claimed in claim 1, wherein as an additive to said fly ash, NaNO3 or Na2CO3 is selectively added depending on circumstances.
5. A method for converting radioactive waste into borosilicate glass form using fly ash, comprising the steps of mixing fly ash or fly ash and silica with a boron oxide or a boron oxide derivative, a metal oxide or a metal oxide-forming salt, and radioactive waste to form a mixture containing up to 65% fly ash by weight; and heating and melting the mixture so as to form a borosilicate glass.
6. A method as claimed in claim 5, wherein fly ash and silica are mixed with the remaining components prior to heating and melting.
7. A method as claimed in claims 5 or 6, wherein the fly ash is purified prior to use.
8. A method as claimed in claims 5, 6 or 7, wherein the composition of the glass-forming mixture, based on oxides, is 10~65wt% of fly ash, 0-45wt% of silica, 10-l7wt% of B203, 10-19wt% of a metal oxide or a metal oxide-forming salt and 5-30wt of radioactive waste.
9. A method as claimed in any one of claims 5-8, wherein the metal oxide or the metal oxide-forming salt is sodium oxide or a sodium oxide-forming salt.
10. A method as claimed in claim 9, wherein the sodium oxide-forming salt is NaNO3 or Na2CO3.
11. A method as claimed in any one of claims 5-10, wherein the boron oxide derivative is H3BO3 or Na2B407.
12. A method as claimed in any one of claims 5-11, wherein the radioactive waste is high level radioactive waste.
13. A method as claimed in any one of claims 5-12, wherein the fly ash is derived from a coal-fired power plant.
14. A borosilicate glass containing radioactive waste obtained by a method as claimed in any one of claims 5-13.
GB9517686A 1995-06-07 1995-08-30 Method for converting high level radioactive waste into glass using fly ash Expired - Fee Related GB2302201B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
KR1019950014954A KR0158083B1 (en) 1995-06-07 1995-06-07 Vitrification method of high radioactive waste material using flyash

Publications (3)

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GB9517686D0 GB9517686D0 (en) 1995-11-01
GB2302201A true GB2302201A (en) 1997-01-08
GB2302201B GB2302201B (en) 1999-05-19

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FR (1) FR2735271B1 (en)
GB (1) GB2302201B (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2012010917A1 (en) * 2010-07-19 2012-01-26 G.I.C. Ipari Szolgáltató És Kereskedelmi Kft. Additive-containing aluminoborosilicate and process for producing the same

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110335695A (en) * 2019-05-27 2019-10-15 西南科技大学 A kind of preparation method of solidification of radwaste basic material and glass solidified body
CN110335693A (en) * 2019-05-27 2019-10-15 西南科技大学 A kind of preparation method for radioactive waste glass solidification basic material and glass solidified body

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1575930A (en) * 1976-12-17 1980-10-01 Kernforschungsz Karlsruhe Method for non-contaminating solidification of radioactive waste materials
GB2157062A (en) * 1984-03-29 1985-10-16 Japan Atomic Energy Res Inst Method of treating waste containing radioactive nuclides
GB2257293A (en) * 1991-06-13 1993-01-06 Doryokuro Kakunenryo Method of volume-reducing vitrification of highlevel radioactive waste

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS61274299A (en) * 1985-05-30 1986-12-04 三菱重工業株式会社 Solidification of radioactive waste
FR2624301B1 (en) * 1987-12-02 1990-03-30 Commissariat Energie Atomique DEVICE FOR CONDITIONING RADIOACTIVE OR TOXIC WASTE CONTAINING BORATE IONS, AND MANUFACTURING METHOD THEREOF
EP0359003B1 (en) * 1988-09-10 1993-12-08 BETEILIGUNGEN SORG GMBH & CO. KG Process for transforming solid, substantially anhydrous waste materials into glass, and apparatus therefor
US4977837A (en) * 1990-02-27 1990-12-18 National Recovery Technologies, Inc. Process and apparatus for reducing heavy metal toxicity in fly ash from solid waste incineration

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1575930A (en) * 1976-12-17 1980-10-01 Kernforschungsz Karlsruhe Method for non-contaminating solidification of radioactive waste materials
GB2157062A (en) * 1984-03-29 1985-10-16 Japan Atomic Energy Res Inst Method of treating waste containing radioactive nuclides
GB2257293A (en) * 1991-06-13 1993-01-06 Doryokuro Kakunenryo Method of volume-reducing vitrification of highlevel radioactive waste

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2012010917A1 (en) * 2010-07-19 2012-01-26 G.I.C. Ipari Szolgáltató És Kereskedelmi Kft. Additive-containing aluminoborosilicate and process for producing the same

Also Published As

Publication number Publication date
KR0158083B1 (en) 1998-12-15
KR970003288A (en) 1997-01-28
FR2735271B1 (en) 1997-08-14
FR2735271A1 (en) 1996-12-13
GB2302201B (en) 1999-05-19
GB9517686D0 (en) 1995-11-01

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PCNP Patent ceased through non-payment of renewal fee

Effective date: 20080830