Cladding for use in nuclear reactors having improved resistance to stress corrosion cracking and corrosion
US6243433A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | May 14, 1999 |
| Grant date | Jun 5, 2001 |
| Priority date | — |
| Expiry date | May 14, 2019 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
An improved fuel element for use in a nuclear reactor comprised of a central core of nuclear material, which is surrounded by a composite cladding. The cladding has an outer metallic tubular portion comprised of well-known cladding alloys used for such purposes. Metallurgically bonded to the outer metallic tubular portion is a commercially pure zirconium microalloyed with a controlled quantity of iron. The zirconium microalloyed with iron produced an inner metallic barrier having a beneficial balance between stress corrosion crack resistance and corrosion resistance while retaining other beneficial properties of pure zirconium, such as ductility.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.