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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Technology
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.
M. Z. Hasan, T. Kunugi
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1030-1035
Blanket Technology | doi.org/10.13182/FST91-A29478
Articles are hosted by Taylor and Francis Online.
Convective heat transfer in the thermally developing region in a coolant 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 MHD fully developed laminar in a circular tube with insulating wall and in the presence of a transverse magnetic field. Both the circumferential variation of the surface heat flux and the presence of a transverse magnetic field greatly affect the steady-state Nusselt number and thermal entry length. At the point where the magnetic field is normal to the tube wall, the steady-state Nusselt number can be increased as much as by a factor of 2 compared with 4.36 for non-MHD flow (parabolic velocity profile) and uniform surface heat flux. The nonuniformity of surface heat flux, on the other hand, can reduce the Nusselt number at the same location (also the point of maximum heat flux) to about 3.0. The transverse magnetic field can increase the thermal entry length by about 40% compared with that for non-MHD flow and uniform heat flux. The nonuniformity of surface heat flux and transverse magnetic field combined can increase the thermal entry length by a factor of 4.6. Neglect of this decrease in Nusselt number can result in an underestimation of the film temperature drop by 38% to 64%. The increase in the entry length would not affect the thermal-hydraulic designs of the first wall and divertor plate because, even with this increase, the entry length is short for liquid-metal coolants.
