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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Latest News
Ontario eyes new nuclear development
A 1,300-acre site left undeveloped on the shores of Lake Ontario four decades ago could see new life as the home to a large nuclear facility.
L. El-Guebaly, M. Elias, B. Madani, C. Martin, E. Marriott, FESS-FNSF Team
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 347-353
Technical Paper | doi.org/10.1080/15361055.2017.1333865
Articles are hosted by Taylor and Francis Online.
The Fusion Nuclear Science Facility (FNSF) is an essential element of the U.S. developmental roadmap to fusion energy. The facility displays the complex integration of tokamak components and subsystems in fusion environment while testing and developing fusion technologies for the U.S. demonstration (DEMO) plant. The integration of the neutronics, shielding, and activation assessments is a key element to the success of FNSF operation. This paper overviews the engineering aspects of the tokamak-based FNSF study and presents an integral scheme that considered the overall configuration, radiation limits, top-level design requirements (including maximizing the tritium breeding ratio), smart selection of low-activation materials for each component, radial build optimization and definition, environmental and safety constraints, and upper temperatures for the reuse of reduced activation ferritic martensitic and bainitic structures after severe loss of coolant accidents.