Detection of fuel rod leakage
US3969187A · kind A · utility
2Cited by
4References
5Claims
0Family size
Assignee
Inventors
Key dates
| Filing date | Dec 6, 1973 |
| Grant date | Jul 13, 1976 |
| Priority date | — |
| Expiry date | Dec 6, 1993 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
Nuclear reactor fuel rod leakage is determined by measurement of vibrational characteristics of a resilient, flexible means sealed within the upper end caps of the fuel elements. The flexible means, which is preferably a metallic diaphragm, is set into motion by the impact of an internal metal rod which is operated by an external magnetic field, thereby permitting an indication of the pressure inside a fuel element without disturbing the welded assembly. The metal rod is activated and the vibration measurements are made through the use of a special tool which fits near the end cap of the fuel element to be tested.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.