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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.
Technical Session|Methods
Monday, April 22, 2024|1:30–3:15PM PDT|Continental Ballroom 2
Session Chair:
Jaako Leppanen (VTT Technical Research Centre of Finland)
Alternate Chair:
Paolo Vinai (Chalmers Univ. Technology)
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Hobbes: Multigroup Cross Section Generation for Mixed-Architecture Computing Environments
1:30–1:50PM PDT
S.J. Douglass (Naval Nuclear Laboratory)
Paper
Understanding the Macroscopic Cross Section Treatment in Hybrid Continuous Energy and Multigroup Depletion Using the Shift Monte Carlo Code
1:50–2:10PM PDT
Vidor Lujan (Georgia Tech), Bailey Painter (Georgia Tech), Inhyung Kim (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley), Thomas M. Evans (ORNL), Tara M. Pandya (ORNL), Dan Kotlyar (Georgia Tech)
Derivation of the History Variable Calculation for Macro-Depletion in Nodal Simulators
2:10–2:30PM PDT
Thomas Folk (Univ. Michigan), Brendan Kochunas (Univ. Michigan)
Initial Assessment of Online Cross Section Generation Capability of Griffin for Gas-Cooled Pebble-Bed Reactor
2:30–2:50PM PDT
Hansol Park (ANL), Yeon Sang Jung (ANL), Changho Lee (ANL), Yaqi Wang (INL), Javier Ortensi (INL)
Application of Expanded Transfer Functions for Predicting Coarse Mesh, One-Group Macroscopic Cross Sections in a 3D Realistic PWR Core
2:50–3:10PM PDT
Bailey Painter (Georgia Tech), Dan Kotlyar (Georgia Tech)
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