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Division Spotlight
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.
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.
Joel Weisman
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 465-469
Technical Note | Reactor | doi.org/10.13182/NT72-A16044
Articles are hosted by Taylor and Francis Online.
Experimental data have shown a high resistance to cross flow in the presence of large axial flows. This phenomenon may be explained by use of a full lateral momentum balance. Application of the momentum balance principle shows that interchannel cross flow at any given level depends on the cross flow at the lower level in addition to the local pressure gradient. This revised procedure for calculation of cross flow should eventually lead to improved estimation of core wide flow redistribution in open lattice cores.
