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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
William R. Sutton III, Dieter J. Sigmar+, George H. Miley
Fusion Science and Technology | Volume 7 | Number 3 | May 1985 | Pages 374-390
Technical Paper | Plasma Engineering | doi.org/10.13182/FST85-A24557
Articles are hosted by Taylor and Francis Online.
An alpha-driven fast magnetosonic wave instability is investigated in tokamak plasmas for propagation transverse to the external magnetic field at frequencies several times the alpha gyrorate. A two-dimensional differential quasi-linear diffusion equation is derived in cylindrical υ⊥-υ∥ geometry. The quasi-linear diffusion coefficients in the small parameter k∥/k⊥ are expanded and the problem is reduced to one dimension by integrating out the υ∥ dependence. Reactor relevant information is obtained using data from the one-dimensional formulation in a 1½-dimensional tokamak transport code. Contour plots of the alpha threshold fraction are used to identify the instability regions in the ne-Ti plane. Alpha/background electron fractions as low as 10−6 to 10−4 may trigger the instability. For a typical reactor-size tokamak, an enhancement of the fraction of the alpha energy transferred to ions by as much as 1.5 can occur for Ti = Te at 7 keV. Still, due to the rapid equilibration of electron and ion temperatures, a < 1 to 2% increase in fusion power occurs overall.