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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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
13th Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2023)
Technical Session
Tuesday, July 18, 2023|10:00–11:45AM EDT|301B
Session Chair:
Linyu Lin
Alternate Chair:
Junyung Kim
Session Organizer:
Jamie B. Coble
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Presentation Slides (Visible to Attendees) — Linyu Lin
Presentation Slides (Visible to Attendees) — Joseph Oncken
Presentation Slides (Visible to Attendees) — Tim Nguyen
Presentation Slides (Visible to Attendees) — Kyle Warns
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Adaptive Data-Driven Model Predictive Control for Heat Pipe Microreactors
10:00–10:25AM EDT
Linyu Lin (INL), Benjamin Zastrow (Univ. Texas, Austin), Joseph Oncken (INL), Vivek Agarwal (INL)
Paper
Adaptive Model Predictive Control for Heat-Pipe-Cooled Microreactors Under Normal and Heat Pipe Failure Conditions
10:25–10:50AM EDT
Joseph Oncken (INL), Linyu Lin (INL), Vivek Agarwal (INL)
Presentation Slides (Visible to Attendees)
Design and Prototyping of Diagnostic Methods to Support Autonomous Operations of Advanced Reactors
10:50–11:15AM EDT
Tat Nghia Nguyen (ANL), Akshay J. Dave (ANL), Roberto Ponciroli (ANL), Richard B. Vilim (ANL)
An Interpretation of the Bellman Equation for Risk-Informed Decision Making
11:15–11:40AM EDT
Kyle Warns (Rensselaer Polytechnic Institute), Asad Ullah Amin Shah (Rensselaer Polytechnic Institute), Junyung Kim (Rensselaer Polytechnic Institute), Hyun Gook Kang (Rensselaer Polytechnic Institute)
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