ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
2020 Winter Meeting and Nuclear Technology Expo
November 15–19, 2020
Chicago, IL|Chicago Marriott Downtown
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 Science and Engineering
Fusion Science and Technology
NEA issues call to action in report on nuclear cost reductions
A new report from the Paris-based OECD Nuclear Energy Agency declares that nuclear power is needed for countries to meet their Paris Agreement decarbonization and energy security policy goals, but that governmental support for a rapid reduction in the cost of new nuclear capacity through the creation of certain policy frameworks is likely necessary.
B. H. Mills, B. Zhao, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 541-545
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST15-116
Articles are hosted by Taylor and Francis Online.
A new helium (He) loop was used to study the helium-cooled modular divertor with multiple jets (HEMJ) at incident heat fluxes q″ ≤ 6.6 MW/m2 as part of the joint US-Japan effort on plasma-facing components evaluation by tritium plasma, heat, and neutron irradiation experiments (PHENIX). These studies were performed at prototypical pressures of 10 MPa and inlet temperatures ranging from 30 °C to 300 °C. The effect of varying the distance between the inner jets cartridge and the outer shell from 0.44 to 0.9 mm was also investigated.
The Nusselt number Nu results for two different tungsten-alloy test sections were in good agreement for q″ = 1.5−6.6 MW/m2. The experiments also suggest that the loss coefficient KL is essentially constant. These Nu and KL results were used to estimate the maximum heat flux q′′max that can be accommodated by the divertor under prototypical conditions and the coolant pumping power as a fraction of the incident thermal power β. The agreement over the broad range of experimental parameters studied suggests that these results at near-prototypical conditions can be extrapolated with reasonable confidence to the operating conditions expected for the HEMJ design.