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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
EnergySolutions to help explore advanced reactor development in Utah
Utah-based waste management company EnergySolutions announced that it has signed a memorandum of understating with the Intermountain Power Agency and the state of Utah to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta, Utah.
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)
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To access paper attachments, you must be logged in and registered for the meeting.
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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