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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
T. Ozawa, T. Abe
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 39-55
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT156-39
Articles are hosted by Taylor and Francis Online.
Annular fuel is very beneficial for fast reactors because of its availability for both high power and high burnup. Most of the annular pellets irradiated up to high burnup showed central-hole shrinkage due to deformation and restructuring during irradiation. This shrinkage has a great influence on power-to-melt, which is a main factor in deciding the maximum power in the fuel design. To predict precisely the central-hole shrinkage during irradiation, the CEPTAR code was developed and verified by using the results of various experiments. In this code, the central-hole diameter is decided in accordance with the law of conservation of mass by using the radial profile of fuel density computed with the void migration model, and its deformation caused by the thermal expansion, swelling, and creep is computed by stress-strain analysis using the approximation of plane strain. Furthermore, this code can also estimate the effect of joint oxide gain (JOG) observed in a gap between the cladding and the fuel pellet with high burnup, which tends to decrease the fuel swelling and to improve the gap conductance due to deposition of solid fission product to the JOG layer. In this paper, an outline of the CEPTAR code and the results of verification are presented.