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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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Modernizing I&C for operations and maintenance, one phase at a time
The two reactors at Dominion Energy’s Surry plant are among the oldest in the U.S. nuclear fleet. Yet when the plant celebrated its 50th anniversary in 2023, staff could raise a toast to the future. Surry was one of the first plants to file a subsequent license renewal (SLR) application, and in May 2021, it became official: the plant was licensed to operate for a full 80 years, extending its reactors’ lifespans into 2052 and 2053.
R. A. Borrelli, Joonhang Ahn, Yongsoo Hwang
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 248-264
Technical Paper | doi.org/10.1080/00295450.2016.1273713
Articles are hosted by Taylor and Francis Online.
Many nations are expanding or initiating nuclear energy programs as part of a national energy portfolio. Transitioning to advanced nuclear energy systems improves sustainability and promotes energy independence. These advanced nuclear energy systems also must be shown to enhance safety, safeguards, and security in order to be realistically deployed. This is of particular concern to non–nuclear weapons states, to assure compliance with International Atomic Energy Agency treaty obligations. Consequently, the relatively new research area of safeguardability addresses how to integrate goals for safety, safeguards, and security as part of a design strategy for an advanced fuel cycle. This paper presents an overall set of principles that form the foundation of a comprehensive safeguardability methodology, including the quantitative modeling studies derived therein. Results show an approach for characterizing used fuel, functional components to engineering design for nuclear materials handling facilities, and repository analysis. We conclude with an argument for the necessity of an integrative, systems assessment approach to the safeguardability of an advanced fuel cycle.