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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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
Latest Journal Issues
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:
Xiaodong Sun
Alternate Chair:
Minghui Chen
Session Organizer:
Brian G. Woods
Staff Producer:
Janet Davis (American Nuclear Society)
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Modelling Assessments of Water Pool Boiling Critical Heat Flux Experiments Under Power Transients
Mingfu He (University of New Mexico), Minghui Chen (University of New Mexico)
Paper
Numerical analysis of wall boiling considering bubble sliding and merge for heat flux partitioning on horizontal tube
Jae Soon Kim (Seoul National University), Hyoung Kyu Cho (Seoul National University)
Presentation Video
Experimental and Numerical analysis of single pump failure in a HLM Reactor
Philippe Planquart (Von Karman Institute), Katrien Van Tichelen (SCK-CEN)
Comparative Analysis for DNBR Between MARS-KS and CTF on the Core Flow Asymmetry
Il Suk Lee (Korea Institute of Nuclear Safety), Dong H. Yoon (Korea Institute of Nuclear Safety), Young S. Bang (Korea Institute of Nuclear Safety), Kwang W. Seul (Korea Institute of Nuclear Safety), Yong C. Kim (Korea University)
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