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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
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Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
Blades-in turbine inspections at Quad Cities set new benchmark for Constellation
When Constellation decided to install replacement Alstom low-pressure turbines at three of its boiling water reactor plants more than 15 years ago, one benefit was knowing the new turbines should operate reliably—and without major inspections—for several years.
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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