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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Ronald F. Kulak
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 378-387
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32574
Articles are hosted by Taylor and Francis Online.
Evaluation of the structural safety of reactors often involves the analysis of various types of fluid-structural components interacting in three-dimensional space. For example, in the design of a pool-type reactor several vital in-tank components such as the primary pumps and the intermediate heat exchangers are contained within the primary tank. Typically, these components are suspended from the deck structure and largely submersed in the sodium pool. Because of this positioning these components are vulnerable to structural damage due to pressure wave propagation in the tank during a hypothetical core disruptive accident. To assess the transient response of these components, it is necessary to perform a dynamic analysis in three-dimensional space that accounts for the fluid-structure coupling. A formulation for a three-dimensional Lagrangian hydrodynamic element was applied to the above safety problem. A model that has many of the salient features of this fluid-structural component system was developed and then analyzed using the NEPTUNE computer code. The primary tank and the in-tank component were modeled as deformable elastoplastic structures, the sodium pool as an inviscid, compressible fluid, while the deck was taken to be rigid and fixed in space. The transient response of the model showed that although the pressure waves loaded the in-tank component so that it moved toward the primary tank, they also loaded the primary tank and moved it away from the component preventing structural damage due to impact between the component and tank.