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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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.
G. Bandyopadhyay
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 62-78
Technical Paper | Fuel | doi.org/10.13182/NT78-A26700
Articles are hosted by Taylor and Francis Online.
To evaluate the role of fission gas in hypothetical core disruptive accidents, experimental and analytical information describing the fission gas behavior in rapid temperature transients is urgently needed. In the present work, a direct-electrical-heating apparatus was used to obtain information on the fission gas behavior and the response of mixed-oxide fuel elements to simulated thermal transient conditions. The experimental results indicate that fission gas response and swelling behavior are strongly dependent on the transient heating rate, and that fission gas can contribute significantly to the failure of a fuel stack during a temperature transient. The microstructural results from these tests were subsequently used to perform a limited verification of the fission gas release and swelling code, FRAS, which was developed to describe the fission gas release behavior in rapid temperature transients. A comparison of the measured intragranular bubble sizes (and in some cases bubble densities) with the calculated bubble sizes (and densities) revealed that the current version of the FRAS code is inadequate in some transient conditions. A nonequilibrium analysis of bubble coalescence may be necessary to describe the fission gas behavior in such temperature transients.