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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.
J. R. Phillips, T. K. Marshall
Nuclear Technology | Volume 36 | Number 2 | December 1977 | Pages 222-228
Technical Paper | International Safeguard / Fuel | doi.org/10.13182/NT77-A31929
Articles are hosted by Taylor and Francis Online.
A precision gamma-scanning system was applied to the nondestructive determination of the isotopic distributions of 103Ru and 106Ru in two failed (U,Pu)O2 fuel pins irradiated in the Experimental Breeder Reactor II. Significant differences in the two distributions were measured that were related to the half-lives of the two ruthenium isotopes. The two distributions can be used to determine the relative times at which the ruthenium deposits were formed within the fuel material. This information may be used to determine nondestructively the changes within the central void region over a period of several irradiation cycles.
