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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.
N. J. Ackermann, Jr., A. R. Buhl
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 320-323
Technical Note | Reactor | doi.org/10.13182/NT71-A31013
Articles are hosted by Taylor and Francis Online.
The polarity spectral coherence method (PSCM) of Seifritz has been proposed for measuring the subcritical reactivity of a nuclear reactor. However, due to the nature of the PSCM measurement technique, a systematic error in the subcritical reactivity measurement may occur due to unexpected changes in the neutron detection efficiency. This error is assessed through the development of the appropriate equations, and a hypothetical measurement in a typical liquid-metal fast breeder reactor is numerically evaluated. The results demonstrate that the PSCM is subject to systematic errors which can be quite serious and which must be considered when the PSCM technique is used.