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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
J. C. Whipple, C. N. Spalaris
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 305-314
Technical Paper | Reactor | doi.org/10.13182/NT76-A31513
Articles are hosted by Taylor and Francis Online.
Three steam generation systems are employed in the Clinch River Breeder Reactor Plant to produce electrical power for delivery to the Tennessee Valley Authority grid. Each steam generator system contains two parallel operating evaporators and one superheater. These vertical shell and tube heat exchangers are arranged in a “hockey stick” configuration and are identical in design except for inlet water orifice inserts added to the evaporators to ensure flow stability. Alloy 2¼ Cr—1 Mo was selected as the material of construction for the sodium-water boundary on the basis of its excellent resistance to water side stress corrosion and fabricability. Development programs are underway to confirm the ability of the steam generators to operate with departure from nucleate boiling, obtain necessary mechanical and physical properties for design, confirm corrosion and decarburization design allowances, and develop reliable fabrication and inservice inspection techniques.