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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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)
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)
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