ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NRC dockets construction permit for Dow, X-energy SMR
The Nuclear Regulatory Commission has accepted Dow’s construction permit application to build an X-energy small modular reactor in Seadrift, Texas.
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.
Register NowLog In
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)
To join the conversation, you must be logged in and registered for the meeting.
