Detection of fuel rod leakage

Details Detection of fuel rod leakage Detection of fuel rod leakage

1973-12-06

1976-07-13

Behrend, Harvey E.

176 19LD, 176 80, G21C 316

Patent

active

039691870

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.

REFERENCES:
patent: 2855355 (1958-10-01), Ohlinger et al.
patent: 3350271 (1967-10-01), Maidment et al.
patent: 3813286 (1974-05-01), Goldman et al.
patent: 3823068 (1974-07-01), Worlton et al.

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