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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
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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Latest News
Constellation seeks rezone for property adjacent to Illinois plant
While no development details have been released, Constellation is asking to rezone 658.8 acres of land it owns around the Byron nuclear plant in Illinois for possible long-term use.
Yasuo Hirose (Retired)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 787-798
The present research intends to investigate some chemical aspects of Molten-Salt Reactors (MSR) specifically in TRU burning application taking a particular interest in the facts under which being misled carelessly by immaturity of the MSR technology as exclusively established for thorium utilization. Topics include density assumption of fuel salt with high actinide concentration; chemical effect of PuF3 fission comparing with that of UF4; suspected validity of the fuel slat as a solution of FLiNaK and an alternative fuel salt constitution procedure. Chemical processes applicable to on-line, front-end and back-end of the Fast Molten Salt Reactor with U-Pu fuel cycle (FMSR-U/Pu) are discussed in encouraging and stimulating its development.