US4152287A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Method for calcining radioactive wastes
Assignee: ExxonMobil Technology and Engineering Co
•
Filing: 1976-11-10
•
Granted: 1979-05-01
•
Expires: 1996-11-10
Abstract
Abstract This invention relates to a method for the preparation of radioactive wastes in a low leachability form by calcining the radioactive waste on a fluidized bed of glass frit, removing the calcined waste to melter to form a homogeneous melt of the glass and the calcined waste, and then solidifying the melt to encapsulate the radioactive calcine in a glass matrix.
Inventors
- 👤 William J. Bjorklund
- 👤 Jack L. McElroy
- 👤 John E. Mendel
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-03 03:45
CPC Classifications
G; G21; G21F; G21F9/00; G21F9/28; G21F9/30; G21F9/301; G21F9/302; G21F9/305
Claims Analysis
Total Claims: 14
Claim 1
Independent Claim
76 words
Process for the calcination of wastes containing radioactive materials which comprises establishing a heated bed of glass forming particles in a reactor, fluidizing the bed by gaseous medium, spraying wastes containing radioactive material into the fluidized bed whereby the metals and fission products in said waste material are calcined on the particles of the bed material and the remaining portion of the waste is vaporized, removing the glass forming particles and calcined waste from the reactor.
Claim 2
Dependent Claim
76 words
Process for the calcination of wastes containing radioactive materials which comprises establishing a heated bed of glass forming particles in a reactor, fluidizing the bed by gaseous medium, spraying wastes containing radioactive material into the fluidized bed whereby the metals and fission products in said waste material are calcined on the particles of the bed material and the remaining portion of the waste is vaporized, removing the glass forming particles and calcined waste from the reactor.
Claim 3
Dependent Claim
13 words
Process according to claim 1 wherein the glass forming particles are glass frit.
Claim 4
Dependent Claim
13 words
Process according to claim 1 wherein the glass forming particles are borosilicate glass.
Claim 5
Dependent Claim
22 words
Process according to claim 1 wherein the size of the glass forming particles have a mean diameter between 200 and 400 microns.
Claim 6
Dependent Claim
20 words
Process of claim 1 wherein the fluidized bed is maintained at a temperature of about 300° C. to 700° C.
Claim 7
Dependent Claim
18 words
Process according to claim 1 wherein the bed is heated by the combustion of fuel in the bed.
Claim 8
Dependent Claim
18 words
Process according to claim 1 further comprising the step of melting said glass forming particles and calcined waste.
Claim 9
Dependent Claim
97 words
Process for the vitrification of radioactive material which comprises establishing a bed of borosilicate glass frit having a mean diameter of between 200 and 400 microns in a reactor, fluidizing said bed with a gaseous medium, heating the bed to a temperature of from 300° C. to 800° C., introducing a liquid waste containing radioactive material into the fluidized bed in an atomized form whereby the radioactive material is calcined on the glass frit, removing the calcine-coated glass frit from the reactor to a melter, melting the radioactive calcined-coated glass frit, and cooling the melted glass-radioactive material.
Claim 10
Dependent Claim
97 words
Process for the vitrification of radioactive material which comprises establishing a bed of borosilicate glass frit having a mean diameter of between 200 and 400 microns in a reactor, fluidizing said bed with a gaseous medium, heating the bed to a temperature of from 300° C. to 800° C., introducing a liquid waste containing radioactive material into the fluidized bed in an atomized form whereby the radioactive material is calcined on the glass frit, removing the calcine-coated glass frit from the reactor to a melter, melting the radioactive calcined-coated glass frit, and cooling the melted glass-radioactive material.
Claim 11
Dependent Claim
16 words
Process according to claim 8 wherein the liquid waste contains ions of metals and fission products.
Claim 12
Dependent Claim
17 words
Process according to claim 8 wherein the metal and fission products are calcined on the glass frit.
Claim 13
Dependent Claim
18 words
Process according to claim 8 wherein the bed is heated by the combustion of kerosene in the bed.
Claim 14
Dependent Claim
18 words
Process according to claim 8 wherein the melted glass-radioactive material is removed from the melter prior to cooling.
References Cited (Backward Citations)
US3479295A
Cited
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1982-04-30 | 1982-10-30 | 1983-05-01 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1986-04-30 | 1986-10-30 | 1987-05-01 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1990-04-30 | 1990-10-30 | 1991-05-01 | $7700.00 | Window Closed / Lapsed |