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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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!
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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Technical Session|Sponsored by RPD
Thursday, November 19, 2020|2:30–4:15PM EST
Session Chair:
Kristin Stolte (Texas A&M Univ.)
Alternate Chair:
Massimiliano Fratoni
Session Organizer:
Pavel V. Tsvetkov
Staff Producer:
Jay Bogardus (American Nuclear Society)
To access the session recording, you must be logged in and registered for the meeting.
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Implementation of Partial Current Discontinuity Factors in VARIANT Nodal Transport Analysis
Puran Deng (University of Michigan Ann Arbor), Won Sik Yang (University of Michigan), Robert N. Wahlen (Niowave, Inc.), Chad P. Denbrock (Niowave Inc.), Terry L. Grimm (Niowave, Inc.)
Paper
Analytic Insights into the Neutronic Characteristics of Neutron Moderators from MCNP Calculations
Donald K. Parsons (Los Alamos)
Energy Deposition in the OpenMC Monte Carlo Particle Transport Code
Paul K. Romano (Argonne National Laboratory), Andrew Johnson (Georgia Institute of Technology), Amanda L. Lund (Argonne National Laboratory), Jingang Liang (Tsinghua University)
Fast Reproduction of Time-dependent MOC Calculations using the Reduced Order Model based on the Proper Orthogonal and Singular Value Decompositions
Kosuke Tsujita (Nuclear Engineering, Ltd.), Tomohiro Endo (Nagoya University), Akio Yamamoto (Nagoya University)
Evaluating Methods for Modeling Disk Fuel Samples with SCALE
Tucker D. Sawyer (University of Texas at Austin), Kevin T. Clarno (University of Texas at Austin)
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