Apparatus for locating defective nuclear fuel elements

Claim 2

An ultrasonic search unit for testing nuclear fuel elements to detect the presence of water in fuel elements spaced within a fuel assembly of the type used in a water cooled nuclear reactor comprising a strip carrier with mutually opposing faces, the strip carrier being dimensioned to freely traverse the spaces between the fuel elements and having an integral aperture, an ultrasonic transducer element, electrodes deposited on at least two sides of the transducer element, the ultrasonic transducer element disposed within the aperture with one of the electrodes being flush with one of the strip carrier faces, means for grounding the ultrasonic transducer element to the strip carrier, means for decoupling said ultrasonic transducer element from the strip carrier, said decoupling means being interposed between the ultrasonic transducer element and the surfaces of the strip carrier defining the aperture, damping means disposed within the aperture adjacent to a recessed portion of the ultrasonic transducer element, and means for energizing the ultrasonic transducer element to transmit an ultrasonic pulse transversely into the wall of the fuel element to be tested.

Claim 3

An ultrasonic search unit as defined by claim 1, wherein the ultrasonic transducer element is a ferroelectric ceramic.

Claim 4

An ultrasonic search unit as defined by claim 2, wherein the ferroelectric ceramic is lead titanate zirconate.

Claim 5

An improved apparatus, for the in situ testing of a nuclear fuel element within a fuel assembly having a plurality of fuel elements closely packed in an array, transversely spaced within the array by spaces on the order of two millimeters, of the type in which an ultrasonic transducer element emits ultrasonic energy into the fuel element under water to detect the presence of water within the fuel element, wherein the improvement comprises: a strip carrier dimensioned to freely traverse the spaces between the fuel elements, the strip carrier having portions defining an integral aperture; the ultrasonic transducer element disposed within the aperture flush with one face of the strip carrier; means for decoupling the ultrasonic transducer element from the strip carrier, said decoupling means being interposed between the ultrasonic transducer element and the surfaces of the strip carrier defining the aperture; damping means disposed within the aperture adjacent to a recessed portion of the ultrasonic transducer element; and means operatively attached to the ultrasonic transducer element for energizing the ultrasonic transducer element to transmit an ultrasonic pulse transversely into the wall of a fuel element to be tested within the fuel assembly.

Claim 6

An improved apparatus, for the in situ testing of a nuclear fuel element within a fuel assembly having a plurality of fuel elements closely packed in an array, transversely spaced within the array by spaces on the order of two millimeters, of the type in which an ultrasonic transducer element emits ultrasonic energy into the fuel element under water to detect the presence of water within the fuel element, wherein the improvement comprises: a strip carrier dimensioned to freely traverse the spaces between the fuel elements, the strip carrier having portions defining an integral aperture; the ultrasonic transducer element disposed within the aperture flush with one face of the strip carrier; means for decoupling the ultrasonic transducer element from the strip carrier, said decoupling means being interposed between the ultrasonic transducer element and the surfaces of the strip carrier defining the aperture; damping means disposed within the aperture adjacent to a recessed portion of the ultrasonic transducer element; and means operatively attached to the ultrasonic transducer element for energizing the ultrasonic transducer element to transmit an ultrasonic pulse transversely into the wall of a fuel element to be tested within the fuel assembly.

Claim 7

The improved apparatus, as set forth in claim 4, further comprising means for measuring a signal corresponding to the ultrasonic echo reflected from the inner wall surface of the fuel element remote from the location of the transducer element and for differentiating between echos transmitted through gas and water.

Claim 10

An apparatus as set forth in claim 6 further comprising an ultrasonic decoupling material disposed between the surfaces of the aperture and the ultrasonic transducer element.

Claim 11

An apparatus as set forth in claim 7 wherein the decoupling material is cork.

Claim 12

An apparatus as set forth in claim 8 wherein the ultrasonic transducer element is a ferroelectric ceramic.

Claim 13

An apparatus as set forth in claim 9 wherein the ferroelectric ceramic is lead titanate zirconate.

Claim 14

An apparatus as set forth in claim 10 wherein the ultrasonic transducer element measures approximately 2.5 millimeters wide, 12.5 millimeters long and 0.3 millimeters thick.

Claim 15

An apparatus as set forth in claim 7 further comprising a sonic damping material, said sonic damping material being disposed in the aperture adjacent the face of the transducer element recessed within the aperture.

Claim 16

An apparatus as set forth in claim 12 wherein the damping material consists essentially of tungsten powder mixed in a low molecular weight polysulfide polymer.

Claim 17

An apparatus as set forth in claim 6 further comprising means for energizing the ultrasonic transducer element to transmit ultrasonic waves in a frequency range of 5 to 15 megahertz.