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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
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!
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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
American Nuclear Society on the firing of NRC Commissioner Hanson
Washington, D.C. — The American Nuclear Society (ANS) issued the following statement:
"A competent, effective, and fully staffed U.S. Nuclear Regulatory Commission is essential to the rapid deployment of new reactors and advanced technologies. The arbitrary removal of commissioners without due cause creates regulatory uncertainty that threatens to delay America’s nuclear energy expansion."
Technical Session|Sponsored by MCD
Tuesday, June 15, 2021|12:00–1:45PM EDT
Session Chair:
Robert E. Grove
Alternate Chair:
Brian C. Kiedrowski
Session Organizer:
Staff Producer:
Janice Lindegard (ANS)
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Direct Computation and Moment-Based Reconstruction of Neutron Multiplicity Distributions
Jawad R. Moussa (Univ. of New Mexico), Anil K. Prinja (Univ. of New Mexico)
Paper
Perturbation-Theory-Based Sensitivity Analysis of Prompt Neutron Decay Constant for Water-Only System
Tomohiro Endo (Nagoya Univ.), Akihiro Noguchi (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency)
Presentation Video (Visible to Attendees)
Manufactured Solutions for Nonlinear, Coupled Neutronics-Thermalhydraulics Problems for Code Verification
Aya Hamdy Hegazy (Univ. of Illinois Urbana-Champaign), Rizwan-uddin (Univ. of Illinois Urbana-Champaign)
Convergent Transport Source Iteration Calculations with Quasi-Monte Carlo
Samuel Pasmann (Univ. of Notre Dame), Ilham Variansyah (Univ. of Notre Dame), Ryan G. McClarren (Univ. of Notre Dame)
Diffusion Theory for Inhomogeneous Neutron Transport Problems in Slab Geometry
Dean Wang (Ohio State Univ.)
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