ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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!
Latest Magazine Issues
Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
W. L. Pearl, E. G. Brush, G. G. Gaul, G. P. Wozadlo
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 235-245
Technical Paper | doi.org/10.13182/NT65-A20508
Articles are hosted by Taylor and Francis Online.
Incoloy-800® fuel-cladding material has been corrosion-tested under heat-transfer conditions at metal temperatures up to 1410° F (766° C) in specially designed out-of-pile superheat facilities. The hydrogen and oxygen contents of the steam were controlled to simulate those found in boiling-water-reactor systems. The corrosion data from the 4000-h heat-transfer tests indicated good corrosion resistance up to at least 1300° F (704° C) metal temperature. A compositionally changed layer developed at the metal-oxide interface. The changed layer depth appeared to be a function of time and temperature of exposure. The descaled weight-loss data for the sheaths operated at a metal temperature of 1100 to 1300° F (593 to 704° C) indicate that greater than 80% of the oxide corrosion product adhered during the first 1000-h exposure, but only about 50% of the total oxidation product remained after 4000 h. The uniform corrosion experienced by the Incoloy-800® when exposed isothermally to 1050 and 1150° F (566 and 621° C) for 10 000h indicates an initially high-corrosion rate that decreases to a lower constant rate within the first 1000 h. An insignificant amount of the oxide was lost to the system.