ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
Latest Magazine Issues
Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Molten salt test loop at INL means real-time data on sensors and materials
The Department of Energy announced March 31 that a new Molten Salt Flow Loop Test Bed at Idaho National Laboratory recently went through its inaugural test run. The closed-loop test system will allow for continuous monitoring and analysis of chloride-based molten salt reactor technology and instruments before the construction of the Southern Company/TerraPower Molten Chloride Reactor Experiment. MCRE—an experimental fast-spectrum molten salt research reactor—will be built at INL’s repurposed Zero Power Physics Reactor, which has been renamed LOTUS (Laboratory for Operation and Testing in the United States).
Technical Session|Evolutionary and Innovative Advanced Technology Fuels (ATF)
Wednesday, October 12, 2022|1:30–3:10PM EDT|Salon A/B
Session Chair:
Hyochan Kim (KAERI)
Alternate Chair:
Jae Ho Yang (KAERI)
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Wrought FeCrAl Alloy (C26M) Cladding Behavior During Burst Experiments and Performance Under LOCA Conditions
1:30–1:55PM EDT
R.T. Sweet (ORNL), C.P. Massey (ORNL), S.B. Bell (Univ. Tennessee., Knoxville), K.A. Kane (ORNL)
Paper
Limiting Degradation Mechanisms for High-Temperature Oxidation Resistance of Promising ATF Cladding Solutions
1:55–2:20PM EDT
Martin Steinbrueck (Karlsruhe Institute of Technology), Mirco Grosse (Karlsruhe Institute for Technology), Chongchong Tang (Karlsruhe Institute of Technology), Juri Stuckert (Karlsruhe Institute of Technology)
Use of Chromium Coating to Provide Protection of Zirconium Cladding at DNB Conditions
2:20–2:45PM EDT
Zeses Karoutas (Westinghouse Electric Co.), Dave Mitchell (Westinghouse Electric Co.), Yixing Sung (Westinghouse Electric Co.), Guoqiang Wang (Westinghouse Electric Co.), William A. Byers (Westinghouse Electric Co.), Michael Conner (Westinghouse Electric Co.)
Assessment of Thin Tube of Alumina-Forming Duplex Stainless Steels (ADSS) as Accident Tolerant Fuel Cladding Materials for Light Water Reactors
2:45–3:10PM EDT
Chaewon Kim (KAIST), Woong Heo (KAIST), Changheui Jang (KAIST), Sung Yong Lee (KEPCO Nuclear Fuel), Hun Jang (KEPCO Nuclear Fuel), Seungjae Lee (KEPCO Nuclear Fuel)
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