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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
F. Warmer, C. D. Beidler, A. Dinklage, Y. Turkin, R. Wolf
Fusion Science and Technology | Volume 68 | Number 4 | November 2015 | Pages 727-740
Technical Paper | doi.org/10.13182/FST15-131
Articles are hosted by Taylor and Francis Online.
In fusion power plant studies, a high confinement improvement with respect to empirical scaling is often assumed in the design of compact machines. In this work, the limits of such a confinement enhancement are studied for a helical-axis advanced stellarator (HELIAS).
As a first exercise, the well-established power balance approach is used to investigate the impact of confinement enhancement (in terms of the ISS04 renormalization factor) on the required size of HELIAS power plants. It is found that both a lower (0.5) and an upper limit (1.5 to 1.7) exist for which, respectively, ignition is no longer possible or further confinement enhancement irrelevant due to physics limits.
In the second part of the work, a predictive neoclassical transport model is introduced and employed to determine a self-consistent confinement time based on transport modelling. It is found that the confinement enhancement with respect to the ISS04 scaling decreases in comparison to Wendelstein 7-X as the device is scaled to reactor size, dropping from ~2.5 to a range of 1.2 to 1.3. This behavior is explained with underlying scaling relations and transport effects. The results from both models are consistent and important for future HELIAS systems studies.