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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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ANS 2025 election is open
The American Nuclear Society election is now open. Members can vote for the Society’s next vice president/president-elect and treasurer as well as six board members (four U.S. directors, one non-U.S. director, and one student director). Completed ballots must be submitted by 1:00 p.m. (EDT) on Tuesday, April 15, 2025.
J. T. Kriese, C. E. Siewert, Y. Yener
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 3-9
Technical Paper | doi.org/10.13182/NSE73-A22582
Articles are hosted by Taylor and Francis Online.
The elementary solutions of the two-group neutron-transport equation are used to solve critical problems for finite slabs and spheres. The half-range orthogonality properties of the basic eigenvectors are used, along with the fundamental H -matrix, to reduce the encountered system of singular integral equations to a system of Fredholm-type equations, and these final equations are solved iteratively to yield accurate predictions of the two-group values of the extrapolated endpoint and critical dimensions for a selected set of slabs and spheres.
