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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
James Corson, Alice Chung, Steven Muller
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 261-268
Research Article | doi.org/10.1080/00295450.2023.2181042
Articles are hosted by Taylor and Francis Online.
This paper presents the Fuel Analysis under Steady-state and Transient (FAST) code contribution to the P2M Simulation Exercise on past fuel melting irradiation experiments organized within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency’s Framework for Irradiated Experiments (FIDES). The benchmark consists of comparisons to two power ramps (xM-3 and HBC-4) that experienced fuel centerline melting. In general, FAST accurately captured the behavior of the fuel rods during the tests, though there are some notable discrepancies between the FAST results and the cladding elongation and fission gas release during the xM-3 power ramp.