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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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May 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Deep Isolation validates its disposal canister for TRISO spent fuel
Nuclear waste disposal technology company Deep Isolation announced it has successfully completed Project PUCK, a government-funded initiative to demonstrate the feasibility and potential commercial readiness of its Universal Canister System (UCS) to manage TRISO spent nuclear fuel.
Technical Session|Sponsored by ETWDD
Wednesday, November 15, 2023|10:00–11:45AM EST|Columbia 12
Session Chair:
Julie Jacobson (INL)
Alternate Chair:
Tyler Newitt (INL)
Session Organizer:
Andrew E. Thomas (INL)
Please join us to listen and learn about student research related to the DOE Nuclear Energy University Program.
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Electrochemical Studies of Actinides in Molten Salt and Aqueous Media in Support of Nuclear Material Management
10:00–10:20AM EST
Bethany Kersten (Case Western Reserve Univ.), Rohan Akolkar (Case Western Reserve Univ.), Christine E. Duval (Case Western Reserve Univ.)
Paper
Analysis of Neutronic Parameters Using MCNP 6.2 for the Molten Salt Irradiation Facility at the PULSTAR Reactor
10:20–10:40AM EST
Matthew Schweitzer (NCSU), Ming Liu (NCSU), Austin Wells (NCSU), Nick Poole (NCSU), Nina Colby Fleming (NCSU), Ayman I. Hawari (NCSU)
Heat Transfer Performance of a Wire-Wrapped Sodium Fast Reactor Fuel Rod Simulator
10:40–11:00AM EST
Nicholas J. Thoreson (Univ. Wisconsin, Madison), Mathieu Martin (TerraPower), Mark H. Anderson (Univ. Wisconsin, Madison)
Optical Basicity Determination of Molten Halide Salts
11:00–11:20AM EST
K. Buttice (Univ. Wisconsin, Madison), A. Couet (Univ. Wisconsin, Madison), R. Gakhar (INL)
Demonstration of Ultrafast Transient Absorption Spectroscopy in Molten Salts
11:20–11:40AM EST
Davis Bryars (NCSU), Alexander W. Bataller (NCSU)
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