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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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Advanced Reactor Safety (ARS)
Technical Session
Monday, June 17, 2024|1:00–2:45PM PDT|Palm A
Session Chair:
Matthew R. Denman
Session Organizer:
Alternate Chair:
Koroush Shirvan
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Quantification of In-Containment Mechanistic Source Term for Advanced Light Water Reactor
1:00–1:20PM PDT
Yahya A. Alzahrani (NCSU), Mihai A. Diaconeasa (NCSU)
Paper
An Assessment of the Applicability and Usability of Light Water Reactor Source Term Software for Non-Light Water Reactor Designers
1:20–1:40PM PDT
Matthew R. Denman (Kairos Power), Peiwen T. Whysall (Kairos Power), Jordan E. Hagaman (Kairos Power)
The Development of Simplified Radionuclide Transport Code (SRT) Version 2.1
1:40–2:00PM PDT
Tyler Starkus (ANL), Dave Grabaskas (ANL), Dong Hoon Kam (ANL), Shayan Shahbazi (ANL)
Consequence Uncertainty Quantification in LMP Applications
2:00–2:20PM PDT
Matthew Humberstone (U.S. Nuclear Regulatory Commission), Hanh Phan (U.S. Nuclear Regulatory Commission), Steven Unwin (PNNL), Steve Short (PNNL), Garill Coles (PNNL)
Presented by Jeffery Wood (U.S. Nuclear Regulatory Commission)
Presentation Slides (Visible to Attendees)
Oxidation Model of the Accident Tolerant Fuel Implemented in NuScale Reactor Using MELCOR Code
2:20–2:40PM PDT
Mohammad Amer Allaf (Univ. Wisconsin, Madison), Grace Ejnik (Univ. Wisconsin, Madison), WooHyun Jung (Univ. Wisconsin, Madison), Michael Corradini (Univ. Wisconsin, Madison), Koroush Shirvan (MIT), Juliana Pacheco Duarte (Univ. Wisconsin, Madison)
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