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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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Leading the charge: INL’s role in advancing HALEU production
Idaho National Laboratory is playing a key role in helping the U.S. Department of Energy meet near-term needs by recovering HALEU from federal inventories, providing critical support to help lay the foundation for a future commercial HALEU supply chain. INL also supports coordination of broader DOE efforts, from material recovery at the Savannah River Site in South Carolina to commercial enrichment initiatives.
Didier Costes
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 169-177
Technical Note | Fission Reactor | doi.org/10.13182/NT84-A33539
Articles are hosted by Taylor and Francis Online.
Sodium-cooled reactor vessels must not resist high pressures, and their walls are relatively thin. These vessels are usually suspended by their lateral wall to the cold roof slab. The upper part of this wall is subjected to periodic thermal stresses and to a permanent tension, corresponding to the weight of the sodium and of the components inside the vessel. In order to avoid a progressive deformation, the temperature of the vessel wall is limited to ∼400°C. This necessitates setting up relatively expensive baffles to isolate the wall from the hot sodium flowing out of the core. In order to relieve the wall from weight-related stresses, vessels resting on the installation basemat by means of sliding or articulated supports were proposed in early projects. A current design proposal consists of resting the vessel bottom on welded, concentric skirts, the chosen temperature of the bottom being relatively low; then a stable thermal gradient appears in sodium layers below the core. The corresponding heat flux lost toward the bottom proves remarkably low; an important simplification of the vessel walls and internal structures, as well as interesting safety features, may be obtained.