US4717434A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Zirconium alloy products
Assignee: Westinghouse Electric Co LLC
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Filing: 1986-03-12
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Granted: 1988-01-05
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Expires: 2006-03-12
Abstract
Abstract It has been found that modifying standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in Zircaloy alloy product having superior high temperature steam corrosion resistance.
Inventors
- 👤 Samuel G. McDonald
- 👤 George P. Sabol
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-10 01:58
CPC Classifications
C; C22; C22F; C22F1/00; C22F1/16; C22F1/18; C22F1/186; G; G21; G21C; G21C3/00; G21C3/02; G21C3/04; G21C3/06; G21C3/07; Y; Y02; Y02E; Y02E30/00; Y02E30/30; Y10; Y10S; Y10S148/00; Y10S148/902; Y10S148/909; Y10S376/00; Y10S376/90
Claims Analysis
Total Claims: 19
Claim 1
Independent Claim
93 words
A final size Zircaloy alloy, nuclear fuel cladding tube comprising: said Zircaloy alloy selected from the group consisting of Zircaloy-2 and Zircaloy-4; a microstructure adjacent to the outer circumferential surface of said fuel cladding tube, said microstructure containing precipitates; said precipitates having an average size below about 1100 angstroms and distributed substantially randomly throughout said microstructure; the outer circumferential surface of said fuel cladding tube characterized by excellent nodular corrosion resistance as evidenced by a uniform, continuous and adherent oxide film after five days exposure to a 454° C. 10.3 MPa steam test.
Claim 2
Dependent Claim
93 words
A final size Zircaloy alloy, nuclear fuel cladding tube comprising: said Zircaloy alloy selected from the group consisting of Zircaloy-2 and Zircaloy-4; a microstructure adjacent to the outer circumferential surface of said fuel cladding tube, said microstructure containing precipitates; said precipitates having an average size below about 1100 angstroms and distributed substantially randomly throughout said microstructure; the outer circumferential surface of said fuel cladding tube characterized by excellent nodular corrosion resistance as evidenced by a uniform, continuous and adherent oxide film after five days exposure to a 454° C. 10.3 MPa steam test.
Claim 3
Dependent Claim
24 words
The final size Zircaloy alloy, nuclear fuel cladding tube according to claim 1 wherein said precipitates have an average size below about 800 angstroms.
Claim 4
Dependent Claim
26 words
The final size Zircaloy alloy, nuclear fuel cladding tube according to claim 1 wherein said microstructure further containing a cold worked and stress relieved grain structure.
Claim 5
Dependent Claim
23 words
The final size Zircaloy alloy, nuclear fuel cladding tube according to claim 3 wherein said precipitates have an average size below 800 angstroms.
Claim 6
Dependent Claim
17 words
The final size Zircaloy alloy fuel cladding tube according to claim 1 further comprising anisotropic crystallographic texture.
Claim 7
Dependent Claim
23 words
The final size Zircaloy alloy, nuclear fuel cladding tube according to claim 5 wherein said precipitates have an average size below 800 angstroms.
Claim 8
Dependent Claim
22 words
The final size Zircaloy alloy, nuclear fuel cladding tube according to claim 1 wherein said microstructure containing a fully recrystallized grain structure.
Claim 9
Dependent Claim
23 words
The final size Zircaloy alloy, nuclear fuel cladding tube according to claim 7 wherein said precipitates have an average size below 800 angstroms.
Claim 10
Dependent Claim
74 words
A final size Zircaloy alloy, water reactor component comprising: said Zircaloy alloy selected from the group consisting of Zircaloy-2 and Zircaloy-4; a microstructure containing precipitates; said precipitates having an average size below about 1100 angstroms and distributed substantially randomly throughout said microstructure; said water reactor component characterized by excellent nodular corrosion rsistance as evidenced by a uniform, continuous and adherent oxide film after five days exposure to a 454° C. 10.3 MPa steam test.
Claim 11
Dependent Claim
74 words
A final size Zircaloy alloy, water reactor component comprising: said Zircaloy alloy selected from the group consisting of Zircaloy-2 and Zircaloy-4; a microstructure containing precipitates; said precipitates having an average size below about 1100 angstroms and distributed substantially randomly throughout said microstructure; said water reactor component characterized by excellent nodular corrosion rsistance as evidenced by a uniform, continuous and adherent oxide film after five days exposure to a 454° C. 10.3 MPa steam test.
Claim 12
Dependent Claim
23 words
The final size Zircaloy alloy water reactor component according to claim 9 wherein said precipitates have an average size below about 800 angstroms.
Claim 13
Dependent Claim
25 words
The final size Zircaloy alloy water reactor component according to claim 9 wherein said microstructure further containing a cold worked and stress relieved grain structure.
Claim 14
Dependent Claim
21 words
The final size Zircaloy water reactor component according to claim 11 wherein said precipitate have an average size below 800 angstroms.
Claim 15
Dependent Claim
17 words
The final size Zircaloy alloy water reactor component according to claim 9 further comprising anisotropic crystallographic texture.
Claim 16
Dependent Claim
21 words
The final size Zircaloy water reactor component according to claim 13 wherein said precipitates have an average size below 800 angstroms.
Claim 17
Dependent Claim
20 words
The final size Zircaloy water reactor component according to clain 9 wherein said microstructure containing a fully recrystallized grain structure.
Claim 18
Dependent Claim
20 words
The final size Zircaloy water reactor component according to clain 9 wherein said microstructure containing a fully recrystallized grain structure.
Claim 19
Dependent Claim
21 words
The final size Zircaloy water reactor component according to claim 15 wherein said precipitates have an average size below 800 angstroms.
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USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
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| 3.5 Years (Year 4) | 1991-01-04 | 1991-07-06 | 1992-01-05 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1995-01-04 | 1995-07-06 | 1996-01-05 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1999-01-04 | 1999-07-06 | 2000-01-05 | $7700.00 | Window Closed / Lapsed |