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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
S. F. Su, Y. Orechwa, H. Henryson II
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 370-382
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32711
Articles are hosted by Taylor and Francis Online.
Two-dimensional multigroup space-time kinetics calculations with thermal-hydraulic feedback were performed for 1000- and 1800-MW(electric) homogeneous and heterogeneous liquid-metal fast breeder reactors. The initiating transient was due to the asymmetric withdrawal of a single control rod. It was found that the point kinetics model can, in many cases, be used for predicting integral reactor characteristics. For accurate predictions of local reactor conditions, space-time kinetics calculations are needed. In the case of both homogeneous and heterogeneous cores, for design basis reactivity insertions with scram, smaller reactivity insertion rates will lead to a greater fuel and cladding temperature rise than large reactivity insertion rates. Heterogeneous cores, because of their inherently greater power shape sensitivity, show a larger temperature rise than the homogeneous cores despite the fact that the transient is of much shorter duration because of an earlier reactor trip due to a lower negative Doppler feedback.