US4126514A
Expired / Lapsed
US
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Method for detecting and locating defective nuclear reactor fuel elements
Assignee: Westinghouse Electric Corp
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Filing: 1976-02-11
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Granted: 1978-11-21
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Expires: 1996-02-11
Abstract
Abstract A method for detecting and locating defective fuel elements in a liquid cooled nuclear reactor employing a sonic/ultrasonic dual test. In accordance with the invention acoustic transducers, sensitive to a broad range of frequencies ranging from the audio to ultrasonic range, are respectively coupled to the exposed top end plugs of the fuel elements of a nuclear reactor fuel assembly. The respective fuel assemblies are voided of coolant, raising the temperature of the individual elements to a point that will boil any liquid coolant present in a defective fuel tube. The audio output of each transducer is translated into a graphic display identifying the presence and location of defective fuel elements. At prescribed intervals passive acoustic monitoring is interrupted for a pulse-echo attenuation measurement of each element. The respective transducers are sequentially energized, communicating pulsed acoustic energy along the fuel element cladding. Attenuation of the acoustic pulses, propagating along the cladding, is highly dependent upon small quantities of moisture in contact with the inside surface of the cladding. The respective transducers monitor attenuation of the reflected energy as a further indication of fuel element defects.
Inventors
- 👤 James W. Wonn
Bibliographic Details
Application Number
—
Jurisdiction
US
Data Source
google_patents
Last Synchronized
2026-11-09 07:15
CPC Classifications
G; G21; G21C; G21C17/00; G21C17/06; G21C17/07; Y; Y02; Y02E; Y02E30/00; Y02E30/30
Claims Analysis
Total Claims: 12
Claim 1
Independent Claim
143 words
A method for detecting and locating a defective nuclear reactor fuel element normally maintained within an assembly having an ordered array of a plurality of spaced fuel elements respectively comprising fissile material enclosed within an acoustically conductive tubular cladding hermetically sealed at either end with the space between fuel elements defining fluid flow channels for the passage of a cooling liquid among the elements of the array, including the steps of: generating an acoustic signal exterior of the cladding; propagating the acoustic signal along the fuel element cladding; monitoring reflections of the propagated signal occurring at a preestablished given location along the axial length of the cladding; and correlating the attenuation of the monitored signal over the amplitude of the generated signal to a preestablished standard corresponding to a level of attenuation indicative of the presence of the cooling liquid within the element.
Claim 2
Independent Claim
143 words
A method for detecting and locating a defective nuclear reactor fuel element normally maintained within an assembly having an ordered array of a plurality of spaced fuel elements respectively comprising fissile material enclosed within an acoustically conductive tubular cladding hermetically sealed at either end with the space between fuel elements defining fluid flow channels for the passage of a cooling liquid among the elements of the array, including the steps of: generating an acoustic signal exterior of the cladding; propagating the acoustic signal along the fuel element cladding; monitoring reflections of the propagated signal occurring at a preestablished given location along the axial length of the cladding; and correlating the attenuation of the monitored signal over the amplitude of the generated signal to a preestablished standard corresponding to a level of attenuation indicative of the presence of the cooling liquid within the element.
Claim 3
Dependent Claim
25 words
The method of claim 1 wherein the generating and monitoring steps are performed by a single ultrasonic transducer which is acoustically coupled to the cladding.
Claim 4
Dependent Claim
60 words
The method of claim 1 for monitoring a plurality of fuel elements within a fuel assembly including the steps of: displaying an output indication of a defective fuel element in response to an indication of the presence of the cooling liquid within the element; and identifying in the display the location within the fuel assembly of the defective fuel element.
Claim 5
Dependent Claim
53 words
The method of claim 1 wherein the tubular cladding is hermetically sealed at either end respectively with an end cap and the acoustic signal generated exterior of the cladding is acoustically coupled at one end through one end cap to the cladding and the reflections monitored are off of the other end cap.
Claim 6
Dependent Claim
103 words
The method of claim 1 wherein the generating and receiving steps are performed within intermittent prescribed intervals including the steps of: substantially isolating the exterior surface of the fuel element cladding from contact with the cooling liquid to the extent necessary to raise the temperature of the element to the degree necessary to boil any moisture within the interior of the fuel cladding; and monitoring the fuel element for audio frequency noise generated from boiling cooling liquid within the fuel element during the period between the intermittent intervals as a further indication of the presence of the liquid cooling medium within the element.
Claim 7
Dependent Claim
27 words
The method of claim 5 wherein the generation and reception of the propagated signal and the reception of the audio noise is performed by a single transducer.
Claim 8
Independent Claim
142 words
A method for detecting and locating a defective nuclear reactor fuel element normally maintained within an assembly having an ordered array of a plurality of spaced fuel elements respectively comprising fissile material enclosed within an internally dry tubular cladding hermetically sealed at either end with the space between fuel elements defining fluid flow channels for the passage of a cooling liquid among the elements of the array, including the steps of: raising the temperature of the fuel element above the boiling point of the cooling liquid by reducing the heat transfer rate from the interior of the fuel element to the exterior of the fuel element cladding below that employed to maintain the fuel element within its prescribed operating temperature band; and monitoring the fuel element end cap for audio frequency noise generated within the fuel element by the boiling cooling liquid.
Claim 9
Independent Claim
142 words
A method for detecting and locating a defective nuclear reactor fuel element normally maintained within an assembly having an ordered array of a plurality of spaced fuel elements respectively comprising fissile material enclosed within an internally dry tubular cladding hermetically sealed at either end with the space between fuel elements defining fluid flow channels for the passage of a cooling liquid among the elements of the array, including the steps of: raising the temperature of the fuel element above the boiling point of the cooling liquid by reducing the heat transfer rate from the interior of the fuel element to the exterior of the fuel element cladding below that employed to maintain the fuel element within its prescribed operating temperature band; and monitoring the fuel element end cap for audio frequency noise generated within the fuel element by the boiling cooling liquid.
Claim 10
Dependent Claim
54 words
The method of claim 7 wherein the temperature of the fuel element is raised by substantially isolating the exterior surface of the fuel element cladding from contact with the cooling liquid to the extent necessary to raise the fuel element temperature to the degree necessary to boil any moisture within the fuel element cladding.
Claim 11
Independent Claim
125 words
A method for detecting a defect in a hermetically sealed internally dry tubular cladding at least partially filled with irradiated ceramic nuclear fuel pellets comprising the steps of: immersing the cladding within a liquid; internally raising the temperature of the cladding above the boiling point of any of the liquid that may be present within the cladding by reducing the heat transfer rate from the interior of the fuel element to the exterior of the fuel element cladding below that employed to maintain the fuel element within its prescribed operating temperature band; and monitoring the cladding for acoustic energy originating from the liquid within the cladding thereby identifying a defect which has enabled the liquid to seep into the normally dry interior of the cladding.
Claim 12
Independent Claim
125 words
A method for detecting a defect in a hermetically sealed internally dry tubular cladding at least partially filled with irradiated ceramic nuclear fuel pellets comprising the steps of: immersing the cladding within a liquid; internally raising the temperature of the cladding above the boiling point of any of the liquid that may be present within the cladding by reducing the heat transfer rate from the interior of the fuel element to the exterior of the fuel element cladding below that employed to maintain the fuel element within its prescribed operating temperature band; and monitoring the cladding for acoustic energy originating from the liquid within the cladding thereby identifying a defect which has enabled the liquid to seep into the normally dry interior of the cladding.
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USPTO Annuity & Maintenance Windows
| Annuity Stage | Window Opens | Payment Deadline | Surcharge Period Until | Estimated Fee | Status |
|---|---|---|---|---|---|
| 3.5 Years (Year 4) | 1981-11-20 | 1982-05-22 | 1982-11-21 | $2000.00 | Window Closed / Lapsed |
| 7.5 Years (Year 8) | 1985-11-20 | 1986-05-22 | 1986-11-21 | $3760.00 | Window Closed / Lapsed |
| 11.5 Years (Year 12) | 1989-11-20 | 1990-05-22 | 1990-11-21 | $7700.00 | Window Closed / Lapsed |