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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
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!
Latest Magazine Issues
Apr 2025
Jan 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Pacific Fusion predicts “1,000-fold leap” in performance, net facility gain by 2030
Inertial fusion energy (IFE) developer Pacific Fusion, based in Fremont, Calif., announced this morning that it is on target to achieve net facility gain—more fusion energy out than all energy stored in the system—with a demonstration system by 2030, and backs the claim with a technical paper published yesterday on arXiv: “Affordable, manageable, practical, and scalable (AMPS) high-yield and high-gain inertial fusion.”
Technical Session|Sponsored by THD
Tuesday, November 17, 2020|2:40–4:20PM EST
Session Chair:
Subash L. Sharma
Alternate Chair:
Guanyi Wang
Session Organizer:
Caleb S. Brooks
Staff Producer:
John Fabian (American Nuclear Society)
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Effect of Subcooling on Phase Angle Difference of Density Wave Instability
Martin A. Lopez de Bertodano (Purdue University)
Paper
Investigation of the Two-Phase Flow Interface Behavior during Quench based on Advanced Imaging Processing
Yue Jin (Massachusetts Institute of Technology), Arunkumar Seshadri (Massachusetts Institute of Technology), Koroush Shirvan (Massachusetts Institute of Technology)
Transient measurement of film boiling during cooldown from CHF in vertical flow
Michelle McCord (University of Illinois), Joseph L. Bottini (University of Illinois Urbana Champaign), Caleb S. Brooks (University of Illinois)
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