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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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2021 Student Conference
April 8–10, 2021
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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W. H. Huang, T. W. Krause, B. J. Lewis
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 452-461
Technical Note | Radiation Measurements and General Instrumentation | dx.doi.org/10.13182/NT11-A13320
Articles are hosted by Taylor and Francis Online.
In the rare occurrence of a fuel failure during normal operation, the primary coolant can enter the element. Visual techniques are normally used for the postirradiation inspection of discharged CANadian Deuterium Uranium (CANDU) fuel bundles to help identify such failures. In this work, a more sensitive method, based on underwater angled-beam ultrasonic inspection, is investigated under laboratory conditions. Only nonirradiated fuel elements were tested. Identification is possible with the introduction of water into the fuel element, which acts as a couplant for sound waves, thereby providing for a clear demarcation of the fuel pellets within the element in observed scans. This study therefore demonstrates that the inspection of the outer-ring (i.e., higher-powered) elements in the complex fuel bundle structure is possible.