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!
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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|Modeling, Analysis, and Methods
Tuesday, October 11, 2022|1:30–3:10PM EDT|Branle
Session Chair:
Ian Porter (GE)
Alternate Chair:
Emmanuel Rouge (IRSN)
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P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments: Main Outcomes on Fuel Melting Assessment in PWR Fuel
1:30–1:55PM EDT
V. D'Ambrosi (CEA), J. Sercombe (CEA), S. Bejaoui (CEA), A. Chaieb (EDF), B. Baurens (EDF), R. Largenton (EDF), A. Ambard (EDF), B. Boer (SCK CEN), G. Bonny (SCK CEN), D. Rozzia (SCK CEN), M. Sevecek (ALVEL), L.E. Herranz (CIEMAT), F. Feria Marquez (CIEMAT), K. Inagaki (CRIEPI), H. Ohta (CRIEPI), F. Boldt (GRS), J. Sappl (GRS), R. Armstrong (INL), A. Mohamad (Japan Atomic Energy Agency), Y. Udagawa (Japan Atomic Energy Agency), C. Cozzo (Paul Scherrer Institute), J. Klouzal (UJV), M. Vitezslav (UJV), J. Corson (U.S. Nuclear Regulatory Commission), J. Peltonen (VTT Technical Research Centre of Finland)
Paper
Hydrogen-Based Transient Cladding Strain Limit
1:55–2:20PM EDT
Timothy M. Crede Jr. (Westinghouse Electric Co.), Julianna L. Schoenwald (Univ. Michigan), Brian L. Mount (Dominion Energy)
Development of PEGASUS™ for Advanced Reactor Applications
2:20–2:45PM EDT
W. Lyon (Structural Integrity Assoc.), W. Liu (Structural Integrity Assoc.), M. Kennard (Structural Integrity Assoc.), D. Nightingale (Structural Integrity Assoc.), D. Jaber (Structural Integrity Assoc.), Y.R. Rashid (Structural Integrity Assoc.)
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