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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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Latest News
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.
Donald J. Dudziak
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 391-392
Technical Note | Reactor | doi.org/10.13182/NT71-A30972
Articles are hosted by Taylor and Francis Online.
The afterheat in a D-T fusion reactor of conventional design is shown to be a serious consideration for loss-of-flow or loss-of-coolant accidents. Some previous estimates of the radioactivation of a niobium vacuum wall and structure are shown to be grossly low. The major additional contributions to the afterheat are from 94mNb, 92mNb, 95Nb, 95mNb, and a long-lived metastable state of93Nb. By considering some of these additional decay sources, the afterheat from a 5-GW(th) D-T reactor of typical design is computed to be at least 30 MW. Early in the reactor lifetime, the decay of the after-heat power should be characterized by the 10.1-day half-life of 92mNb. A qualitative review of the activation cross sections of molybdenum, an alternate possibility as a structural material, does not give expectation of decay powers significantly lower than niobium.