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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Comments on U.S. nuclear export controls on China
As trade negotiations are in the works between the United States and China, Washington, D.C., has the advantage in semiconductors but nuclear power is a different story, according to a June 9 article in the Hong Kong–based South China Morning Post.
K. H. Beckurts
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 516-522
Technical Paper | doi.org/10.13182/NSE57-A25417
Articles are hosted by Taylor and Francis Online.
The pulse method has been applied to problems of neutron diffusion in graphite. By measuring the decay constant of the neutron flux emanating from various graphite pile geometries, the diffusion coefficient and the absorption cross section can be determined with great precision. In comparison to an exponential experiment, the quantity of graphite necessary for an accurate determination of the diffusion length can be considerably reduced. The finite geometry of the moderator gives rise to a diffusion-cooling effect on the neutron equilibrium temperature which can be understood quantitatively by a direct measurement of the heat transfer from the neutron gas to the lattice. In the second part of the work, the pulse method is used to determine the influence of eccentric control rods on the buckling of a cylindrical reactor model.
