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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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.
A. J. Lovell
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 323-331
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31198
Articles are hosted by Taylor and Francis Online.
The effects of fast reactor irradiation on the creep behavior of annealed Type 316 stainless steel were reviewed and the interrelation between creep response and irradiation-induced microstructure development was analyzed. The effects of neutron fluence, irradiation temperature, and test temperature on creep response were studied using illustrative examples. The results indicate that use of creep data from unirradiated specimens for design purposes over estimates strain expected during irradiation, except when a component is stressed at low temperature following high temperature irradiation.
