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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 RPD
Tuesday, June 9, 2020|2:30–4:15PM EDT
Session Chair:
Zeyun Wu (Virginia Commonwealth Univ.)
Alternate Chair:
Pavel V Tsvetkov (LANL)
Session Organizer:
Track Organizer:
Staff Producer:
Jessica Vazquez (American Nuclear Society)
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To access paper attachments, you must be logged in and registered for the meeting.
Advances in MCNP for Reactor Calculations
R. B. Wilkerson (LANL), G. W. McKinney (LANL), C. J. Josey (LANL), M. E. Blood (LANL), J. D. Galloway (LANL), J. C. Armstrong (LANL), H. R. Trellue (LANL)
Paper
Single Channel Design Based on Artificial Intelligence for Molten Salt Reactors
Mehmet Turkmen (Univ. of Illinois), Kathryn D. Huff (Univ. of Illinois)
Development of FRENDY Nuclear Data Processing Code: Generation Capability of Multi-group Cross Sections from ACE File
Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency)
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