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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
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Nominations open for CNTA awards
Citizens for Nuclear Technology Awareness is accepting nominations for its Fred C. Davison Distinguished Scientist Award and its Nuclear Service Award. Nominations for both awards must be submitted by August 1.
The awards will be presented this fall as part of the CNTA’s annual Edward Teller Lecture event.
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)
To access the session recording, you must be logged in and registered for the meeting.
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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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