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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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55th annual Nuclear News Buyers Guide now available
For American Nuclear Society members and Nuclear News subscribers, the 2024 Buyers Guide is now available in the ANS Digital Nuclear Library. The print version will be mailed along with the May “Capacity Factors/Nuclear Security” issue of Nuclear News magazine.
The corresponding ANS online Buyers Guide database is available year-round to all readers—updated with the latest products, services, and suppliers contact information for more than 600 nuclear-related companies.
L. Bromberg, D.R. Cohn, E. Bobrov, N. Diatchenko, R.J. LeClaire, J.E. Meyer, J.E.C. Williams
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 264-269
Alternate Fuels | doi.org/10.13182/FST83-A22879
Articles are hosted by Taylor and Francis Online.
DD-DT operation could provide a significant reduction in tritium breeding requirements in high field tokamak reactors without requiring very large increases in reactor size or plasma beta. Operation with the tritium breeding requirement is of particular interest. The reduced tritium breeding requirement makes possible the use of blanket designs which might be difficult to implement in a DT reactor (for example, LiAl2O3 blankets). The reduced blanket requirement could also be used for excess tritium production. Tradeoffs between tritium breeding and plasma performance requirements are investigated. Illustrative design features are developed for devices using both resistive magnets and superconducting magnets. Parameters for the device with superconducting magnets are BT = 7 T, β = 0.063, R = 9.6 m, a = 2.4 m, γ = 0.8, and Pwall = 2.2 MW/m2.