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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
T. Kunugi, M. Z. Hasan
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1024-1029
Blanket Technology | doi.org/10.13182/FST91-A29477
Articles are hosted by Taylor and Francis Online.
Convective heat transfer in the thermally developing region in a circular channel of the first wall and limiter/divertor plates of a fusion reactor has been analyzed numerically. The surface heat flux on a coolant channel in these plasma facing components varies circumferentially. The flow is assumed non-MHD fully-developed laminar and turbulent in a circular tube. The nonuniformity of surface heat flux greatly affect the Nusselt number and thermal entry length. For the cosine distribution of surface heat flux, the steady-state Nusselt number can be reduced at the point of maximum heat flux by as much as 38%, 62% and 37% for fully-developed laminar Poiseuille, laminar slug and turbulent flows, respectively. Thermal entry length can be increased by up to 2.4 times for laminar flow and 3.5 times for turbulent flow due to the nonuniformity of surface heat flux. If this reduction of Nusselt number due to the nonuniformity of surface heat flux is disregarded, the film temperature drop in the coolant channels of plasma facing components of a fusion reactor will be underestimated by 37% to 62%. This will result in an underestimation of the maximum structure temperature. The increase in entry length is not likely to affect the thermal-hydraulic design of a conventional divertor plate.