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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jan 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
Technical Session|Sponsored by THD
Tuesday, June 13, 2023|10:00–11:45AM EDT|Marriott 2
Session Chair:
Hitesh Bindra (Purdue)
Alternate Chair:
Piyush Sabharwall (INL)
Session Organizer:
Wade R. Marcum
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Impacts of Primary Heat Exchanger Design on Heat Pipe Microreactor Power Conversion (revised September 2023)
10:00–10:20AM EDT
Curtis Foster (Univ. Wisconsin, Madison), Ian Jentz (Univ. Wisconsin, Madison), Gregory F. Nellis (Univ. Wisconsin, Madison), Mark Anderson (Univ. Wisconsin, Madison)
Paper
Preliminary Evaluation of Thermal Performance for Spent Fuel Pool Passive Cooling System with Thermosyphon and Water Jacket
10:20–10:40AM EDT
Min Suk Lee (KAIST), Sanghoon Lee (KAIST), Wooseong Park (KAIST), Yong Hoon Jeong (KAIST)
Numerical Study of Fission Particle Transport in Ventilation Ducts in Nonreactor Nuclear Facilities: Case Study of Circular and Square Ducts with T-Junctions
10:40–11:00AM EDT
Thien Nguyen (ORNL), William McCarter (ORNL), Scott Nelson (ORNL), Joanna McFarlane (ORNL)
Graphite Dust Facilitated FP Transport Investigation for Improvement of Deposition Models
11:00–11:20AM EDT
R. Chavez (TAMU), M. Stephenson (TAMU), N.K. Anand (TAMU), Y.A. Hassan (TAMU), Mitchell Stephenson (TAMU)
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