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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Kentucky legislature sends nuclear bills to governor
Kentucky’s Republican-majority legislature passed a bill this past week that could bring nuclear energy to the “coal-is-king” state as lawmakers broadly seek solutions to reduce carbon emissions. The bill went to Democratic Gov. Andrew Beshear on Monday for final approval.
F. Bonelli, L. V. Boccaccini, B.-E. Ghidersa, Q. Kang, L. Savoldi, R. Zanino
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 507-511
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-985
Articles are hosted by Taylor and Francis Online.
The first 3D thermal-fluid-dynamic and structural analyses done for the design and pre-test assessment of the so-called Thermo-Cycle Mock-up (TCM), reproducing about 0.3 m2 of a flat first wall (FW) with relevant helium cooling channels, are presented, based also on previous computational and experimental activities conducted at KIT but limited so far to a single cooling channel with straight heated length. The TCM is the first of a series of FW mock-ups presently under construction, to be tested starting from 2015 in the large HELOKA facility at KIT. Here, the fluid dynamics in the 180° turns of the TCM cooling channels is investigated together with the effects of heat transfer between neighboring channels, when the plate is subject to steady-state heat fluxes in the range 0.3-0.5 MW/m2. Based on the computed temperature maps, the stresses in the TCM and the related damage figures for the main failure modes (i.e., ratcheting and creep/fatigue) are assessed. These are compared with allowable limits in code and standards for the qualification of the TCM design and related to the prediction of the behavior of the component in the actual fusion environment.