Patent US4084945A successfully refreshed from Google Patents.
US4084945A
Expired / Lapsed
US
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Entrainment separator apparatus
Assignee: Ecodyne Corp
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Filing: 1976-08-02
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Granted: 1978-04-18
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Expires: 1996-08-02
Abstract
Abstract A liquid-gas separator may be used with a liquid concentrator for returning entrained liquid. The separator employs serially arranged mesh pads of different cross-sectional areas. The largest pad is closest to the liquid-gas inlet, and the smallest pad is closest to the gas outlet.
Inventors
- 👤 Anthony N. Chirico
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-10-29 09:18
CPC Classifications
G; G21; G21F; G21F9/00; G21F9/04; G21F9/06; G21F9/08; B; B01; B01D; B01D1/00; B01D1/30; B01D1/305
Claims Analysis
Total Claims: 3
Claim 1
Independent Claim
165 words
A method of disposing of a variable volume flow of aqueous radioactive waste, comprising: heating the waste until the water component vaporizes; passing the vapors and any entrained radioactive water droplets at a varying range of velocities serially through a plurality of water droplet separators having decreasing cross-sectional areas in the direction of vapor flow; the velocity at which said vapors and entrained radioactive water droplets pass through said water droplet separators varying with said variable volume of flow; one of said water droplet separators having a relatively small cross-sectional area being most effective in removing radioactive water droplets when the vapor velocity is at the low end of said range, and another of said water droplet separators having a relatively large cross-sectional area being most effective in removing radioactive water droplets when the vapor velocity is at the high end of said range; removing decontaminated vapors; returning the radioactive water droplets to the waste being heated; and removing concentrated radioactive waste water for disposal.
Claim 2
Independent Claim
165 words
A method of disposing of a variable volume flow of aqueous radioactive waste, comprising: heating the waste until the water component vaporizes; passing the vapors and any entrained radioactive water droplets at a varying range of velocities serially through a plurality of water droplet separators having decreasing cross-sectional areas in the direction of vapor flow; the velocity at which said vapors and entrained radioactive water droplets pass through said water droplet separators varying with said variable volume of flow; one of said water droplet separators having a relatively small cross-sectional area being most effective in removing radioactive water droplets when the vapor velocity is at the low end of said range, and another of said water droplet separators having a relatively large cross-sectional area being most effective in removing radioactive water droplets when the vapor velocity is at the high end of said range; removing decontaminated vapors; returning the radioactive water droplets to the waste being heated; and removing concentrated radioactive waste water for disposal.
Claim 3
Dependent Claim
46 words
The method of claim 1, wherein said vapors and entrained radioactive water droplets are passed vertically through said water droplet separators; and separated water falls under the influence of gravity into a radioactive water collecting zone from which it is returned to said waste being heated.
References Cited (Backward Citations)
US3208204A
Cited
US2788080A
Cited
US3119674A
Cited
US3626672A
Cited
DE2020871A1
Cited
US3721069A
Cited
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1981-04-17 | 1981-10-17 | 1982-04-18 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1985-04-17 | 1985-10-17 | 1986-04-18 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1989-04-17 | 1989-10-17 | 1990-04-18 | $7700.00 | Window Closed / Lapsed |