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Division Spotlight
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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
John W. Prados, J. L. Scott
Nuclear Technology | Volume 3 | Number 8 | August 1967 | Pages 488-494
Technical Paper and Note | doi.org/10.13182/NT67-A27780
Articles are hosted by Taylor and Francis Online.
The Prados-Scott model for coated-particle behavior has been modified to include the effects of irradiation-induced creep on the stress-strain history of pyrolytic-carbon coatings. Calculations are performed in a stepwise fashion, with double trial-and-error iterations required for each time (or fluence) increment. Lack of accurate information on the mechanical behavior of pyrolytic carbons under irradiation still limits the quantitative applicability of the results; however, the computational sequence has been designed to permit simple updating of mechanical behavior subroutines as more reliable data are obtained. Using the best available creep information, we found that the performance of typical pyrolytic-carbon-coated particles is significantly improved by creep under conditions of irradiation which will obtain in advanced high-temperature gas-cooled reactors. On the other hand, with the high burnup rates and low fast fluences characteristic of most coated-particle proof tests, the effects of creep are small and are likely to be undetectable. In such cases, an elastic model can be used effectively to predict failure.