Published August 2, 1977
| Version v1
Patent
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Detection of fuel rod leakage
Creators
Description
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. 5 claims, 8 figures
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- IPC:
- Int. Cl.G21C17/00.
- IPC
- Int. Cl.G21C17/00.
- Patent number
- US patent document 4,039,375/A/
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9365838
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- FAILED ELEMENT DETECTION; FAILED ELEMENT MONITORS; FUEL ELEMENTS; SPECIFICATIONS
- Descriptors DEC
- REACTOR COMPONENTS