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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
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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May 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
MURR expansion set back by Mo. state legislature
Spirits were high last month when a ribbon cutting was held at the University of Missouri for a $20 million, three-story, 47,000-square-foot addition, dubbed MURR West, to the MURR research reactor facilities.
Technical Session|Sponsored by THD
Monday, June 8, 2020|3:30–5:15PM EDT
Session Chair:
Wade R. Marcum
Alternate Chair:
Seung Jun Kim
Session Organizer:
Jun Fang (ANL)
Track Organizer:
Igor Bolotnov (NCSU)
Staff Producer:
Jessica Vazquez (American Nuclear Society)
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Improvement of Advanced Nuclear Reactor Safety Analysis Codes Using CFD
Rohan Biwalkar (Pittsburgh Technical LLC), Sola Talabi (Pittsburgh Technical LLC), Kenneth Redus (Redus and Associates LLC)
Paper
CFD Modeling of Hot-Channel for Potential High-Power Configuration of Missouri S&T Reactor
Thaqal Alhuzaymi (King Abdulaziz City for Science and Technology), Ayodeji B. Alajo (Missouri Univ. Science and Technology), Joshua Schlegel (Missouri Univ. Science and Technology)
Study on Selecting Conservative Axial Power Shape for DNBR Design Limit
Shane Park (KEPCO Nuclear Fuel)
Presentation Video (Visible to Attendees)
Theoretical Exploration of Heat Transfer Characteristics of Liquid Metals
Yaou Shen (Nuclear Power Institute of China), Shinian Peng (Nuclear Power Institute of China), Mingyu Yan (Nuclear Power Institute of China), Yu Zhang (Nuclear Power Institute of China), Jian Deng (Nuclear Power Institute of China)
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