US4440862A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Method of determining corrosion properties of zirconium alloys
Assignee: General Electric Co
•
Filing: 1981-10-30
•
Granted: 1984-04-03
•
Expires: 2001-10-30
Abstract
Abstract Means for discriminating the corrosion susceptibility of alloys of zirconium in an environment of a water cooled, nuclear fission reactor.
Inventors
- 👤 Bo-Ching Cheng
- 👤 Ronald B. Adamson
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-10-25 13:26
CPC Classifications
G; G01; G01N; G01N17/00; Y; Y10; Y10S; Y10S436/00; Y10S436/908
Claims Analysis
Total Claims: 13
Claim 1
Independent Claim
149 words
A method of determining the relative resistance to nodular-type of corrosion of an alloy of zirconium in an environment of a water cooled nuclear fission reactor, comprising exposing a specimen of the alloy to high pressure steam sequentially applied at two distinct temperature levels by applying the steps of: (a) subjecting a specimen of an alloy of zirconium to an atmosphere of steam at a temperature of about 300° to about 420° C. at a pressure of at least about 1000 psig for a period of at least about 5 hours; (b) thereupon subjecting the specimen of an alloy of zirconium at an atmosphere of steam at a temperature of about 490° to about 520° C. at a pressure of at least about 1000 psig for a period of at least about 12 hours; and (c) ascertaining any corrosion formation on said steam exposed specimen of alloy of zirconium.
Claim 2
Independent Claim
149 words
A method of determining the relative resistance to nodular-type of corrosion of an alloy of zirconium in an environment of a water cooled nuclear fission reactor, comprising exposing a specimen of the alloy to high pressure steam sequentially applied at two distinct temperature levels by applying the steps of: (a) subjecting a specimen of an alloy of zirconium to an atmosphere of steam at a temperature of about 300° to about 420° C. at a pressure of at least about 1000 psig for a period of at least about 5 hours; (b) thereupon subjecting the specimen of an alloy of zirconium at an atmosphere of steam at a temperature of about 490° to about 520° C. at a pressure of at least about 1000 psig for a period of at least about 12 hours; and (c) ascertaining any corrosion formation on said steam exposed specimen of alloy of zirconium.
Claim 3
Dependent Claim
27 words
The method of claim 1, wherein the specimen is exposed to the steam atmosphere of step (a) for a period of about 5 to about 15 hours.
Claim 4
Dependent Claim
27 words
The method of claim 1, wherein the specimen is exposed to the steam atmosphere of step (b) for a period of about 12 to about 30 hours.
Claim 5
Dependent Claim
75 words
The method of claim 1, wherein the specimen of an alloy of zirconium is subjected to an atmosphere of steam within an autoclave under a pressure of about 1000 to about 1500 psig while at a temperature of about 300° to about 420° C. for a period of about 5 to about 10 hours, followed by a temperature of about 490° to about 520° C. for a period of about 16 to about 24 hours.
Claim 6
Independent Claim
119 words
A method of determining the relative resistance to corrosion of an alloy of zirconium in an environment of a water cooled nuclear fission reactor, comprising subjecting a specimen of an alloy of zirconium to high pressure steam sequentially applied at two distinct temperature levels including an atmosphere of steam within an autoclave and a pressure of about 1000 to about 1500 psig for a period of about 5 to about 15 hours at a temperature of about 300° to about 420° C., and thereafter for a period of about 12 to about 30 hours at a temperature of about 490° to about 520° C., then ascertaining any weight increase in said steam exposed specimen of an alloy of zirconium.
Claim 7
Independent Claim
119 words
A method of determining the relative resistance to corrosion of an alloy of zirconium in an environment of a water cooled nuclear fission reactor, comprising subjecting a specimen of an alloy of zirconium to high pressure steam sequentially applied at two distinct temperature levels including an atmosphere of steam within an autoclave and a pressure of about 1000 to about 1500 psig for a period of about 5 to about 15 hours at a temperature of about 300° to about 420° C., and thereafter for a period of about 12 to about 30 hours at a temperature of about 490° to about 520° C., then ascertaining any weight increase in said steam exposed specimen of an alloy of zirconium.
Claim 8
Dependent Claim
56 words
The method of claim 5, wherein the specimen is subjected to steam at a temperature of about 300° to about 420° C. for a period of about 5 to about 10 hours and thereafter to steam at a temperature of about 490° to about 520° C. for a period of about 16 to about 24 hours.
Claim 9
Dependent Claim
50 words
The method of claim 5, wherein the specimen is subjected to steam at a temperature of about 400° C. for a period of about 5 to about 15 hours and thereafter to steam at a temperature of about 500° C. for a period of about 12 to about 30 hours.
Claim 10
Independent Claim
141 words
A method of determining the relative resistance to corrosion of an alloy of zirconium in an environment of a water cooled nuclear fission reactor core, comprising subjecting a specimen of an alloy of zirconium to an atmosphere of steam within an autoclave applied sequentially at two distinct temperature levels in the following sequence of conditions: (a) an atmosphere of steam at a temperature of about 300° to about 420° C. at a pressure of about 1000 to about 1500 psig for a period of about 5 to about 10 hours; (b) thereafter an atmosphere of steam at a temperature of about 490° to about 520° C. at a pressure of about 1000 to about 1500 psig for a period of about 16 to 24 hours, (c) then ascertaining any weight increase in said steam exposed specimen of the alloy of zirconium.
Claim 11
Independent Claim
141 words
A method of determining the relative resistance to corrosion of an alloy of zirconium in an environment of a water cooled nuclear fission reactor core, comprising subjecting a specimen of an alloy of zirconium to an atmosphere of steam within an autoclave applied sequentially at two distinct temperature levels in the following sequence of conditions: (a) an atmosphere of steam at a temperature of about 300° to about 420° C. at a pressure of about 1000 to about 1500 psig for a period of about 5 to about 10 hours; (b) thereafter an atmosphere of steam at a temperature of about 490° to about 520° C. at a pressure of about 1000 to about 1500 psig for a period of about 16 to 24 hours, (c) then ascertaining any weight increase in said steam exposed specimen of the alloy of zirconium.
Claim 12
Dependent Claim
46 words
The method of claim 8, wherein the specimen is exposed to an atmosphere of steam at about 400° C. for a period of about 8 to about 10 hours and thereafter to steam at about 500° C. for a period of about 16 to 24 hours.
Claim 13
Dependent Claim
55 words
The method of claim 8, wherein the specimen comprises an alloy of zironium composed of at least about 95% by weight of zirconium and including in percent by weight of up to about 0.2% of tin, up to about 0.5% of iron, up to about 0.5% of chromium and 0 to about 0.15% of nickel.
References Cited (Backward Citations)
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1987-04-03 | 1987-10-03 | 1988-04-03 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1991-04-03 | 1991-10-03 | 1992-04-03 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1995-04-03 | 1995-10-03 | 1996-04-03 | $7700.00 | Window Closed / Lapsed |