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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
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A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
M. D. Hageman, D. L. Sadowski, M. Yoda, S. I. Abdel-Khalik
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 228-232
Divertor & High Heat Flux Components | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST10-232
Articles are hosted by Taylor and Francis Online.
The helium-cooled plate-type divertor can reduce the number of divertor modules while accommodating heat fluxes q" up to 10 MW/m2 incident on tungsten-alloy armor. Dynamically similar experimental studies were performed to evaluate the thermal performance of variants of this divertor design at conditions that spanned the prototypical operating Reynolds number Re of 3.3 × 104. In the studies, a jet of air issuing from 0.5 mm and 2 mm wide slots impinged on and cooled a heated planar surface 2 mm away from the slot, then flowed through either a 2 mm wide channel or an array of cylindrical pin fins. The studies indicate that the fins, which increase the cooled surface area by a factor of 3.76, increase the effective heat transfer coefficient (HTC) by as much as 160% at a relatively modest increase in pressure drop of less than 40%.These experimental results were used to determine the thermal performance of the actual plate design with helium cooling under prototypical conditions. Although the benefit of the fins is reduced because the fin efficiency decreases as the HTC increases, the predictions suggest that the fins could increase the maximum q" that can be accommodated by this design to ~18 MW/m2. Alternatively, for a given heat flux (e.g. 10 MW/m2), adding fins could allow operation of the divertor at lower coolant flow rates, and hence pumping powers.