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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Mar 2025
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Nuclear Science and Engineering
April 2025
Nuclear Technology
March 2025
Fusion Science and Technology
Latest News
Report spotlights energy sector’s growing nuclear investment
As part of a broader series on the future of global energy markets, S&P Global has released a report on examining the growing interest in nuclear power as the solution to many of the problems the energy sector faces.
To read the full details and conclusions of the report, click here.
Technical Session|Monte Carlo Methods and Applications
Monday, April 28, 2025|1:00–2:40PM MDT|Lawrence B
Session Chair:
Elliott Biondo (ORNL)
Alternate Chair:
David Griesheimer (Naval Nuclear Laboratory)
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A Hybrid Cross Section Generation Method Using Monte Carlo Codes for Nuclear Thermal Propulsion Nodal Diffusion Analysis
1:00–1:25PM MDT
Jake Smith (Georgia Tech), Dan Kotlyar (Georgia Tech)
Paper
Clarification on the Various Methods of Calculating the P1 Transport Cross Section Using Monte Carlo Codes
1:25–1:50PM MDT
Vidor H. Lujan (Georgia Tech), Bailey Painter (Georgia Tech), Dan Kotlyar (Georgia Tech)
Multigroup Cross Section Generation with the Shift Monte Carlo Code
1:50–2:15PM MDT
Tara M. Pandya (ORNL), Friederike Bostelmann (ORNL), Donny Hartanto (ORNL), Steven P. Hamilton (ORNL), Matthew A. Jessee (ORNL), Nicholas P. Luciano (ORNL), Tarek Ghaddar (ORNL)
Implementation of the Iterated Fission Probability Method in OpenMC to Compute Adjoint-Weighted Kinetics Parameters
2:15–2:40PM MDT
Joffrey Dorville (ANL), Luke Labrie-Cleary (Copenhagen Atomics), Paul K. Romano (ANL)
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