Thermal-mechanical treatment of composite nuclear fuel element cladding
US4390497A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | Sep 21, 1981 |
| Grant date | Jun 28, 1983 |
| Priority date | — |
| Expiry date | Sep 21, 2001 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldMaterials, metallurgy
- WIPO sectorChemistry
Abstract
Cladding for nuclear fuel elements which is formed with a zirconium metal barrier layer bonded to the inside surface of a zirconium alloy tube and which is sized by a cold working tube reduction process and is heat treated after final reduction at a temperature and for a time period which allows substantially complete recrystallization of the zirconium metal barrier layer and provides a fine-grained microstructure therein and which stress-relieves but does not fully recrystallize the zirconium alloy tube. The crystallographic structure of the zirconium metal barrier layer may be improved by compressive deformation such as shot-peening.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.