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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
Kin Wah Wong, Vijay K. Dhir, W. E. Kastenberg
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 121-137
Technical Paper | Reactor | doi.org/10.13182/NT78-A32073
Articles are hosted by Taylor and Francis Online.
A mechanistic model that describes events leading to in-channel fuel plateout following fuel pin failure under slow transient overpower accident conditions has been proposed. The thermal and hydraulic effects of the plated out fuel have also been investigated. Results based on this model indicate that during a slow transient overpower accident (2.4 cent/s), in-core fuel freezing and channel plugging can be expected to occur. The extent of fuel freezing and channel plugging is sensitive to fuel particle size, the amount of fuel injected, and the amount of fission gas injected into the coolant channel The results are also compared with experimental data from the TREAT H-4 experiment.
