ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
MURR expansion set back by Mo. state legislature
Spirits were high last month when a ribbon cutting was held at the University of Missouri for a $20 million, three-story, 47,000-square-foot addition, dubbed MURR West, to the MURR research reactor facilities.
Technical Session
Wednesday, May 18, 2022|3:30–5:15PM EDT|Brighton I/II
Session Chair:
Michael T. Wenner
Alternate Chair:
William J. Marshall
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
Horizontal Split Table Conceptual Design for Advanced Reactor Validation
Mathieu N. Dupont (ORNL), Justin B. Clarity (ORNL), Daniel J. Siefman (LLNL), Catherine M. Percher (LLNL)
Paper
Expanded Validation of Uranium Systems with the KENO Monte Carlo Codes and SCALE 6.2.4
W.J. Marshall (ORNL), O.M. Belcher (US Naval Academy), N.H. Byrne (US Naval Academy), L.E. de Leon (US Naval Academy), M.N. Solis (US Naval Academy), T.M. Greene (ORNL), S.R. Blair (US Naval Academy)
Uncertainty Quantification in Neutron Noise Analysis Using Monte-Carlo Markov Chain Methods: An Application to Nuclear Waste Drum Assay
Paul Lartaud (CEA), Philippe Humbert (CEA), Josselin Garnier (CMAP)
Benchmark of Neutron Thermalization in Graphite Using a Pulsed Slowing-Down-Time Experiment
E. Lee (NCSU), N.C. Fleming (NCSU), A.I. Hawari (NCSU)
To join the conversation, you must be logged in and registered for the meeting.
