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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
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Nov 2024
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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Technical Session|Methods
Wednesday, April 24, 2024|3:30–5:15PM PDT|Continental Ballroom 1
Session Chair:
Kazuya Yamaji (Mitsubishi Heavy Industries)
Alternate Chair:
Kyoung Lee (ORNL)
Session Organizer:
Go Chiba (Hokkaido University)
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Pathline Reformulation of the Delayed Neutron Precursors Equation
3:30–3:50PM PDT
Mathis Caprais (CEA), Daniele Tomatis (newcleo), Nathan Greiner (CEA), André Bergeron (CEA)
Paper
Presentation Slides (Visible to Attendees)
Transport of Highly Volatile Gases Related to Noble Gases and Tritium in the MSRE
3:50–4:10PM PDT
Kyoung O. Lee (ORNL), David Kropaczek (ORNL), Jorge Navarro (ORNL)
Nuclear Heating Benchmark in Molten Salt Fast Reactor
4:10–4:30PM PDT
A. Chambon (Technical Univ. Denmark), E.P. Senstius (Technical Univ. Denmark), N. Moret (Technical Univ. Denmark)
Benchmarking Between Fuel Cycle Codes and Nuclear Data Evaluations for Decay Heat After a Uranium-233 Fission Pulse
4:30–4:50PM PDT
Riko Okuyama (Hokkaido Univ.), Go Chiba (Hokkaido Univ.), Sebastien Lahaye (CEA)
A Numerical Study of the Similarity Between the Decay Heat of PWR and SFR MOX Fuels
4:50–5:10PM PDT
D. Da Cunha (CEA), J.-F. Lebrat (CEA), F. Nguyen (CEA), V. Vallet (CEA)
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