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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
January 2025
Nuclear Technology
Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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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