Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods
Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350.degree. C. to 750.degree. C., and a second additive having a solubility in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350.degree. C. to 750.degree. C. and a solubility of the second additive in the first additive over the temperature range extending from 350.degree. C. to 750.degree. C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC07-05ID14517
- Assignee:
- Battelle Energy Alliance, LLC (Idaho Falls, ID)
- Patent Number(s):
- 8,831,166
- Application Number:
- 13/021,480
- OSTI ID:
- 1156951
- Country of Publication:
- United States
- Language:
- English
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RESEARCH ON ZIRCONIUM ALLOYS WITH NIOBIUM AND/OR SILICON WITH A VIEW TO THEIR USE AS CLADDING MATERIAL IN WATER-COOLED NUCLEAR REACTORS. Quarterly Report No. 4, January 1, 1961-March 31, 1961
NUCLEAR ENGINEERING DEPARTMENT PROGRESS REPORT FOR SEPTEMBER 1-DECEMBER 31, 1959