ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
R. H. Renshaw, S. Roy
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 371-382
Technical Paper | Materials | doi.org/10.13182/NT55-371
Articles are hosted by Taylor and Francis Online.
Twelve steam generators in three nuclear power plants were damaged during manufacture by postweld stress relief heat treatment. This damage was detected after all were installed, but before any of the plants became operational. The steam generators were rebuilt, in situ, by complete replacement of the internals and tubing. The damage caused by heat treatment consisted of indentation of the tubing by distortion of the tube support plates. The indentations produced points of local high stress in the tubing, causing a potential for stress corrosion cracking. The indentations and the distortion of the support plates also prevented free axial motion of the tubing through the support plates in service, and it is thought that some tubes would have failed in service for this reason. The rebuilding program permitted design changes to accommodate technical information accumulated since the vessels were designed in 1975. These design changes principally were a strengthening of internal structural members to resist seismic forces and fluid forces predicted for pipe breaks, substitution of stainless steel for carbon steel tube support plates, a more elastic U-bend restraint design, increase of some clearances to better tolerate in-service thermal distortion, and a redesigned emergency water injection system to promote thermal syphoning of the reactor coolant under accident conditions. New methods of tube expansion, tube-to-tube-sheet welding, and heat treatment of the tubing were developed to facilitate field installation. The work required 15 months. It was planned and executed so that the delays to the erection programs of the plants were minimized. The final result was a significant improvement in the design of the steam generators, and an accumulation of technology that may be useful if steam generators should require in-service retubing.