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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2022)
August 7–10, 2022
Marco Island, FL|JW Marriott Marco Island
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 2022
Jan 2022
Latest Journal Issues
Nuclear Science and Engineering
July 2022
Nuclear Technology
Fusion Science and Technology
Latest News
Carbon value: Lifetime extensions of nuclear reactors could save billions in climate mitigation costs
On the road to achieving net-zero by midcentury, low- or no-carbon energy sources that slash carbon dioxide emissions are critical weapons. Nevertheless, the role of nuclear energy—the single largest source of carbon-free electricity—remains uncertain.
Nuclear energy, which provides 20 percent of the electricity in the United States, has been a constant, reliable, carbon-free source for nearly 50 years. But our fleet of nuclear reactors is aging, with more than half of the 92 operating reactors across 29 states at or over 40 years old—the length of the original operating licenses issued to the power plants. While some reactors have been retired prematurely, there are two options for those that remain: retire them or renew their license.
Technical Session
Wednesday, May 18, 2022|3:30–5:15PM EDT|Brighton I/II
Session Chair:
Michael T. Wenner
Alternate Chair:
William J. Marshall
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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)
Summary
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)
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