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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
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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
J. D. Galambos, Y-K. M. Peng, L. J. Perkins
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1463-1468
ITER | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29547
Articles are hosted by Taylor and Francis Online.
The nominal International Thermonuclear Experimental Reactor (ITER) configuration is a double-null (DN) divertor, which requires precise plasma vertical position control. Vertical displacements of only about 1 cm (out of a plasma height of 4.7 m) are estimated to destroy the up/down symmetric distribution of power flow to the divertor plates. As an alternate configuration to avoid this difficulty, we look at the single-null (SN) option, where all the charged power flow is deposited on the lower divertor plate. The primary consideration in this study is that of technology phase performance (maximum neutron wall load) for the ITER divertor heat load and plasma constraints. With regard to the divertor heat loads, the SN case has the advantages of (a) longer scrape-off field line connection lengths and (b) more vertical space, which allows a greater spreading of the heat load on the divertor plates. These advantages offset the SN case disadvantage of having fewer divertor plates, and therefore the potential for higher heat fluxes for a given core plasma condition. The attainable wall loads for the SN and DN divertors are found to be similar for steady-state and hybrid operation scenarios.