Patent US4485652A successfully refreshed from Google Patents.
Patent US4020131A successfully refreshed from Google Patents.
US4020131A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Preparation of mixed oxide nuclear fuel
Assignee: Atomic Energy of Canada Ltd AECL
•
Filing: 1975-12-01
•
Granted: 1977-04-26
•
Expires: 1995-12-01
Abstract
Abstract A method of making mixed oxide especially UO 2 -PuO 2 nuclear fuel by impregnation wherein the green pellets of nuclear fuel oxide are partially sintered, then impregnated with a second nuclear fuel oxide, and then given a final and complete sintering step.
Inventors
- 👤 Melville A. Feraday
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-07 13:36
CPC Classifications
G; G21; G21C; G21C3/00; G21C3/42; G21C3/58; G21C3/62; G21C3/623; Y; Y02; Y02E; Y02E30/00; Y02E30/30
Claims Analysis
Total Claims: 5
Claim 1
Independent Claim
110 words
A method of making enriched mixed oxide nuclear fuel comprising: a. sintering green oxide fuel pellets of a first nuclear fuel material in a first stage of sintering until the pellets have a 3-25% open porosity, said sintering being carried out at a temperature in the range 1100° to 1400° C, b. grinding off the outer surface layer of the pellets, c. impregnating the pellets with a salt of a second nuclear fuel material in solution, and d. subjecting the impregnated pellets to a second stage of sintering in the temperature range 1500° to 1700° C to convert the salt of the second nuclear material to oxide of the material.
Claim 2
Independent Claim
110 words
A method of making enriched mixed oxide nuclear fuel comprising: a. sintering green oxide fuel pellets of a first nuclear fuel material in a first stage of sintering until the pellets have a 3-25% open porosity, said sintering being carried out at a temperature in the range 1100° to 1400° C, b. grinding off the outer surface layer of the pellets, c. impregnating the pellets with a salt of a second nuclear fuel material in solution, and d. subjecting the impregnated pellets to a second stage of sintering in the temperature range 1500° to 1700° C to convert the salt of the second nuclear material to oxide of the material.
Claim 3
Dependent Claim
29 words
A method as in claim 1 wherein the fuel pellets are made of a first nuclear fuel material selected from the group consisting of uranium oxide and thorium oxide.
Claim 4
Dependent Claim
19 words
A method of making enriched mixed oxide nuclear fuel as in claim 1 wherein the said salt is nitrate.
Claim 5
Dependent Claim
32 words
A method of making enriched mixed oxide nuclear fuel as in claim 1 wherein the said second nuclear fuel material is selected from the group consisting of plutonium, uranium -233, and uranium-235.
References Cited (Backward Citations)
US3327027A
Cited
US3320178A
Cited
US3408304A
Cited
US3531416A
Cited
US3789013A
Cited
US3728274A
Cited
US3799882A
Cited
US3806565A
Cited
USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1980-04-25 | 1980-10-25 | 1981-04-26 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1984-04-25 | 1984-10-25 | 1985-04-26 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1988-04-25 | 1988-10-25 | 1989-04-26 | $7700.00 | Window Closed / Lapsed |