GB2048555A - Plutonium waste fixation - Google Patents
Plutonium waste fixation Download PDFInfo
- Publication number
- GB2048555A GB2048555A GB7915298A GB7915298A GB2048555A GB 2048555 A GB2048555 A GB 2048555A GB 7915298 A GB7915298 A GB 7915298A GB 7915298 A GB7915298 A GB 7915298A GB 2048555 A GB2048555 A GB 2048555A
- Authority
- GB
- United Kingdom
- Prior art keywords
- block
- glaze
- cement
- wastes
- firing
- 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.)
- Withdrawn
Links
- 239000002699 waste material Substances 0.000 title claims abstract description 16
- 229910052778 Plutonium Inorganic materials 0.000 title claims description 3
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 title claims description 3
- 239000004568 cement Substances 0.000 claims abstract description 20
- 238000000034 method Methods 0.000 claims abstract description 17
- 239000002901 radioactive waste Substances 0.000 claims abstract description 17
- 239000007787 solid Substances 0.000 claims abstract description 14
- 238000010304 firing Methods 0.000 claims abstract description 13
- 239000004927 clay Substances 0.000 claims abstract description 11
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 claims abstract description 7
- 239000000203 mixture Substances 0.000 claims description 8
- 239000002002 slurry Substances 0.000 claims description 8
- 239000000919 ceramic Substances 0.000 claims description 4
- 239000010453 quartz Substances 0.000 claims description 4
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N silicon dioxide Inorganic materials O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 4
- 229910052768 actinide Inorganic materials 0.000 claims description 2
- 150000001255 actinides Chemical class 0.000 claims description 2
- 229910052810 boron oxide Inorganic materials 0.000 claims description 2
- 229910052791 calcium Inorganic materials 0.000 claims description 2
- 239000011575 calcium Substances 0.000 claims description 2
- -1 calcium aluminates Chemical class 0.000 claims description 2
- 230000006835 compression Effects 0.000 claims description 2
- 238000007906 compression Methods 0.000 claims description 2
- JKWMSGQKBLHBQQ-UHFFFAOYSA-N diboron trioxide Chemical compound O=BOB=O JKWMSGQKBLHBQQ-UHFFFAOYSA-N 0.000 claims description 2
- 239000006185 dispersion Substances 0.000 claims description 2
- 238000001035 drying Methods 0.000 claims description 2
- 230000000694 effects Effects 0.000 claims description 2
- 230000004927 fusion Effects 0.000 claims description 2
- 238000002386 leaching Methods 0.000 claims description 2
- 238000000465 moulding Methods 0.000 claims description 2
- 239000011148 porous material Substances 0.000 claims description 2
- 238000011268 retreatment Methods 0.000 claims description 2
- 239000002904 solvent Substances 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 2
Classifications
-
- 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
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
-
- 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
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
- G21F9/304—Cement or cement-like matrix
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Environmental & Geological Engineering (AREA)
- Chemical & Material Sciences (AREA)
- Inorganic Chemistry (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
A process for the containment of radioactive wastes involves fixing the wastes in a high-alumina cement, firing to form an integral solid body and glazing the surface of the solid body. A clay can be included with the cement to assist the glazing step.
Description
SPECIFICATION
Plutonium waste fixation
The present invention concerns the containment or fixing of radioactive waste products.
Many processes have been proposed for the containment or fixing of radioactive wastes and resulting in products which are stable and safe. The final products should satisfy a number of conditions and in particular they should be (a) chemically inert (b) monolithic form so that dispersion to the environment is difficult (c) resistant to leaching by known solvents (d) preferably capable of retreatment should it become necessary to recover the radioactive wastes.
According to the present invention a process for the containment of radioactive wastes comprises fixing the wastes in a high-alumina cement, firing to form an integral solid body and glazing the surface of the solid body.
Preferably, a clay is included with the cement to provide a smooth surface finish to the solid body and to assist in the application of the glazing.
High-alumina cement which comprises calcium aluminates has desirable green and fired properties.
Its setting and hardening times are approximately 4 and 8 hours respectively and ceramic bonding is induced on firing to temperatures in excess of about 1 000 C.
The invention will be described further, by way of example, with reference to the following embodiment.
A mixture of high-alumina cement, radioactive waste and clay is blended and hydrated to form a slurry. The slurry is vibrated in a mould and cured in a damp atmosphere. The composition can comprise 40% cement, 50% waste and 10% clay, preferably a whiteware clay. Such a composition is derived on the basis of friability, surface finish and drying properties.
After curing, the resulting block is fired at a temperature of about 1 000"C for approximately 2 hours to remove all combined water and to induce ceramic bonding. The block is then coated wtih a glaze and glostfired to about 1010"C for about 10 minutes. The glaze is a thin glassy layer formed on the surface of the block to seal the outer pores. For best finish it is desirable that the applied glaze is in compression, that is, the block should possess a greater coefficient of thermal expansion than the glaze. This condition is insured by the addition of approximately 20% quartz in the glaze solution which has the effect of reducing the thermal expansion coefficient of the glaze to below that of the block.The preferred glazes are coloured, leadless varieties which contain metallic stains and a low boron oxide content. Such glazes have a high viscosity value at the fusion temperature and provide a better coverage of the block.
It is important to achieve a smooth surface finish on the green block and to avoid holes which could result in blow-holes in the glaze. The thickness of the glaze applied to the block can be about 0.5 mm.
The radioactive wastes can be actinide containing wastes, such as ash from incineration or crushed contaminated glassware. Conveniently, the cement/ waste slurry is moulded into a flat cylindrical block prior to the application of the glaze. However, other shapes of block are clearly possible. The invention is not restricted to the composition percentages given in the above example nor to the particular firing temperatures and times.
1. A process for the containment of radioactive wastes characterised by fixing the wastes in highalumina cement, firing to form an integral solid body and glazing the surface of the solid body.
2. A process according to claim 1 characterised by including a clay with the cement to provide a smooth surface finish to the solid body and to assist in the application of the glazing.
3. A process according to claim 2 characterised by moulding a cement/waste slurry into a block, curing and thereafter firing the block.
4. A process according to claim 3 characterised by firing the block at a temperature in the region of 1 0000C for approximately 2 hours.
5. A process according to claim 1, characterised by including 20% quartz in the glaze to reduce the thermal expansion coefficient of the glaze to below that of the block.
6. A process for the containment of radioactive wastes according to claim 1 and substantially as herein particularly described.
**WARNING** end of DESC field may overlap start of CLMS **.
Claims (6)
1. A process for the containment of radioactive wastes characterised by fixing the wastes in highalumina cement, firing to form an integral solid body and glazing the surface of the solid body.
2. A process according to claim 1 characterised by including a clay with the cement to provide a smooth surface finish to the solid body and to assist in the application of the glazing.
3. A process according to claim 2 characterised by moulding a cement/waste slurry into a block, curing and thereafter firing the block.
4. A process according to claim 3 characterised by firing the block at a temperature in the region of 1 0000C for approximately 2 hours.
5. A process according to claim 1, characterised by including 20% quartz in the glaze to reduce the thermal expansion coefficient of the glaze to below that of the block.
6. A process for the containment of radioactive wastes according to claim 1 and substantially as herein particularly described.
Priority Applications (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB7915298A GB2048555A (en) | 1979-05-02 | 1979-05-02 | Plutonium waste fixation |
| DE19803015885 DE3015885A1 (en) | 1979-05-02 | 1980-04-24 | METHOD FOR BINDING RADIOACTIVE WASTE |
| JP5772480A JPS55151299A (en) | 1979-05-02 | 1980-04-30 | Plutonium waste fixation |
| FR8009876A FR2455784A1 (en) | 1979-05-02 | 1980-04-30 | METHOD FOR CONTAINING RADIO-ACTIVE WASTE |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB7915298A GB2048555A (en) | 1979-05-02 | 1979-05-02 | Plutonium waste fixation |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB2048555A true GB2048555A (en) | 1980-12-10 |
Family
ID=10504912
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB7915298A Withdrawn GB2048555A (en) | 1979-05-02 | 1979-05-02 | Plutonium waste fixation |
Country Status (4)
| Country | Link |
|---|---|
| JP (1) | JPS55151299A (en) |
| DE (1) | DE3015885A1 (en) |
| FR (1) | FR2455784A1 (en) |
| GB (1) | GB2048555A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0071927A1 (en) * | 1981-08-07 | 1983-02-16 | Forschungszentrum Jülich Gmbh | Process for solidifying radioactive wastes |
| GB2130784A (en) * | 1982-10-07 | 1984-06-06 | Ronald Leslie Attwell | Filling interstices between pieces of material |
| WO2006047070A1 (en) * | 2004-10-22 | 2006-05-04 | Studsvik, Inc. | In-container mineralization |
| US7531152B2 (en) | 2000-10-19 | 2009-05-12 | Studsvik, Inc. | Mineralization of alkali metals, sulfur, and halogens |
| US10593437B2 (en) | 2015-01-30 | 2020-03-17 | Studsvik, Inc. | Methods for treatment of radioactive organic waste |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3219114A1 (en) * | 1982-05-21 | 1983-11-24 | Kernforschungsz Karlsruhe | METHOD FOR IMPROVING THE PROPERTIES OF RESTORATION OF RADIOACTIVE FASTE WASTE |
| JPS58218696A (en) * | 1982-06-15 | 1983-12-19 | 株式会社東芝 | Method of processing radioactive waste |
| JPS61191999A (en) * | 1985-02-20 | 1986-08-26 | 動力炉・核燃料開発事業団 | Method of stabilizing and treating uranium slag or uranium smelting waste slag |
| JP2014235024A (en) * | 2013-05-31 | 2014-12-15 | 株式会社Ｅ＆Ｅテクノサービス | Manufacturing method of solidified body, and solidified body manufactured by the same |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3093593A (en) * | 1958-07-14 | 1963-06-11 | Coors Porcelain Co | Method for disposing of radioactive waste and resultant product |
| NL235423A (en) * | 1959-01-19 | |||
| FR1246848A (en) * | 1959-10-13 | 1960-11-25 | Commissariat Energie Atomique | Process for the disposal of radioactive waste and products obtained by this process |
| US3988258A (en) * | 1975-01-17 | 1976-10-26 | United Nuclear Industries, Inc. | Radwaste disposal by incorporation in matrix |
| DE2726087C2 (en) * | 1977-06-10 | 1978-12-21 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Process for the final disposal-ready, environmentally friendly solidification of "and moderately radioactive and / or actinide-containing, aqueous waste concentrates or of fine-grained solid waste suspended in water |
-
1979
- 1979-05-02 GB GB7915298A patent/GB2048555A/en not_active Withdrawn
-
1980
- 1980-04-24 DE DE19803015885 patent/DE3015885A1/en not_active Withdrawn
- 1980-04-30 JP JP5772480A patent/JPS55151299A/en active Pending
- 1980-04-30 FR FR8009876A patent/FR2455784A1/en not_active Withdrawn
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0071927A1 (en) * | 1981-08-07 | 1983-02-16 | Forschungszentrum Jülich Gmbh | Process for solidifying radioactive wastes |
| GB2130784A (en) * | 1982-10-07 | 1984-06-06 | Ronald Leslie Attwell | Filling interstices between pieces of material |
| US7476194B2 (en) | 1999-10-20 | 2009-01-13 | Studsvik, Inc. | In-container mineralization |
| US7531152B2 (en) | 2000-10-19 | 2009-05-12 | Studsvik, Inc. | Mineralization of alkali metals, sulfur, and halogens |
| WO2006047070A1 (en) * | 2004-10-22 | 2006-05-04 | Studsvik, Inc. | In-container mineralization |
| US10593437B2 (en) | 2015-01-30 | 2020-03-17 | Studsvik, Inc. | Methods for treatment of radioactive organic waste |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2455784A1 (en) | 1980-11-28 |
| JPS55151299A (en) | 1980-11-25 |
| DE3015885A1 (en) | 1980-11-13 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| WAP | Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1) |