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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand Resort
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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Fusion Science and Technology
OPG, Microsoft to work toward net-zero future for Ontario
Ontario Power Generation and Microsoft Canada have formed a partnership aimed at combatting climate change and driving sustainable growth across the province of Ontario, the Canadian utility announced this week.
Under the partnership, Microsoft will procure clean energy credits (CECs) sourced from OPG’s nuclear and hydro assets in Ontario on an hourly basis. (OPG’s nuclear assets include the four-unit Darlington plant and six-unit Pickering facility.) According to the announcement, this will enable Microsoft to advance toward its 100/100/0 by 2030 goal, which commits the software firm to powering its data centers globally with zero-carbon energy, 24/7.
Wednesday, May 18, 2022|3:30–5:15PM EDT|Brighton I/II
Michael T. Wenner
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)
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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