Leak detector probe for fuel rods

Measuring and testing – Moisture content or absorption characteristic of material

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Details

73 672, 176 19LD, 176 80, G01N 2900, G21C 1706

Patent

active

039759490

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 and the vibration measurements are made by a special tool which fits over the end cap of the fuel element to be tested.

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patent: 3638053 (1972-01-01), Schenk et al.
patent: 3641811 (1972-02-01), Gnaedinger, Jr. et al.
patent: 3685350 (1972-08-01), Pettinato
patent: 3762496 (1973-10-01), Milberger et al.
patent: 3813286 (1974-05-01), Goldman et al.
patent: 3823068 (1974-07-01), Worlton et al.

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