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Division Spotlight
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.
Meeting Spotlight
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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Latest News
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
Sadek Hossain Nishat, Md. Hossain Sahadath, Farhana Islam Farha
Nuclear Science and Engineering | Volume 196 | Number 5 | May 2022 | Pages 623-636
Technical Note | doi.org/10.1080/00295639.2021.2003644
Articles are hosted by Taylor and Francis Online.
A thermal-hydraulic study of an isolated Advanced Gas-Cooled Reactor (AGR) nuclear fuel rod with smooth and rough cladding surfaces is carried out by computational fluid dynamics simulation and analytical calculation. Square transverse ribs of various pitch/height ratios (6:12) are considered for the rough surface. Parameters of the rough cladding surface show greater values than those for the smooth surface except for surface heat flux. It is found that only the average surface heat flux increases with an increasing pitch/height ratio. On the other hand, the average values of wall shear stress, Darcy friction factor, skin friction factor, convective heat transfer coefficient, Nusselt number, and thermal-hydraulic performance decrease with an increasing pitch/height ratio. The simulated results are found to be very close to the values obtained from an analytical calculation. Also, square and circular ribs are compared. The circular ribs show lower values of convective heat transfer coefficient and wall shear stress but permit high surface heat flux. The results of this study will help researchers comprehend the effect of cladding surface roughness on fuel rod thermal behavior.