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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Wednesday, June 15, 2022|10:15AM–12:00PM PDT|Redondo
Session Chair:
Minghui Chen
Alternate Chair:
Qiuping Lv
Session Organizer:
W. David Pointer
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Modeling of a Nitrate Salt Natural Circulation Loop
Sheng Zhang (Univ. Michigan), Xiaodong Sun (Univ. Michigan)
Paper
Numerical Methodology for Design and Evaluation of Natural Circulation Systems for MSR Applications
J.S. Narváez Arrúa (Politecnico di Milano), A. Cammi (Politecnico di Milano), S. Lorenzi (Politecnico di Milano), P.R. Rubiolo (Univ. Grenoble Alpes)
Determination of Aspect Ratio Influence on Flow and Heat Transfer Behavior in Twisted Elliptical Tubes for Molten Salt Applications
S. Tutwiler (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.), Dillon R. Shaver (ANL)
Numerical Investigation of Cartridge Heater Performance Applied to the FASTR Main Heater for Molten Chloride Salts
Nolan Goth (ORNL), Thien Nguyen (ORNL), Kevin Robb (ORNL), Ethan Kappes (ORNL)
Investigating Thermal Hydraulics Performance of a New Test Section Designed for the LSTL FLiNaK Using CFD
Ethan Kappes (ORNL), Thien Duy Nguyen (ORNL), Kevin Robb (ORNL)
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