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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2022)
August 7–10, 2022
Marco Island, FL|JW Marriott Marco Island
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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September 2022
Nuclear Technology
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August 2022
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American Nuclear Society supports IAEA’s condemnation of attack on Ukraine nuclear power plant
Statement from American Nuclear Society President Steven Arndt and Executive Director and CEO Craig Piercy:
Technical Session|Panel|Sponsored by FCWMD|Cosponsored by NNPD
Wednesday, June 16, 2021|11:00AM–12:45PM (12:00–1:45PM EDT)
Session Chair:
Benjamin B. Cipiti
Session Organizer:
Alternate Chair:
Michael Browne
Staff Producer:
Mich Leana (ANS)
The Material Protection Accounting and Control Technologies program has completed a 2020 milestone to demonstrate Safeguards and Security by Design (SSBD) for a notional electrochemical reprocessing facility. The work has been outlined in a series of nine papers in a special issue of the Journal of Nuclear Materials Management. This panel session will describe key lessons learned from the SSBD process, the materials accountancy and physical protection approach, measurement technology development, and experimental testing. The approach and tools used in this work can be applied to other nuclear fuel cycle facilities in the future.
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