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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
June 2025
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Latest News
NWMO chooses vendors for Canadian repository
Canada’s Nuclear Waste Management Organization has selected five companies it is to work with to design and plan the organization’s proposed deep geologic repository for spent nuclear fuel. As the owner of the project, the NWMO will be working with WSP Canada, Peter Kiewit Sons (Kiewit), Hatch Ltd., Thyssen Mining Construction of Canada, and Kinectrics.
Technical Session|Panel|Sponsored by FCWMD|Cosponsored by NNPD
Wednesday, June 16, 2021|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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